Fission core and multiplicative conversion for thermal and electrical generation

Description

46 Fission and Multiplicative Conversion Core for Thermal and Electrical Generation Field of invention

[0001] The present invention relates to the field of nuclear engineering, specifically to nuclear reactor cores, and the possibility of converting fertile elements into fissile elements, nuclear fission, and generating heat and electricity for residential and industrial purposes. Fundamentals of the invention

[0002] Nuclear reactors, equipped with uranium U235-based cores maintained in critical or subcritical conditions, with thermal or fast spectra, have been in operation for over seven decades, representing established technologies in thermonuclear power generation.

[0003] In general, fuel elements in thermal reactor cores consist of multiple fuel rods with a 1-1.5 cm pitch filled with uranium ceramic pellets. These fuel rods are held together in rectangular or hexagonal arrangements, immersed in a moderator and coolant, which may be light water or different combinations such as light water / heavy water, graphite / CO2, graphite / water vapor, among others.

[0004] The reactor cores are heterogeneous, with separate fuel and moderator components. In a thermal reactor, the fast neutrons from the fission of U235 escape to the moderator, slowing down to thermal energies, and then returning by diffusion to the pellets in the fuel rods where they are absorbed or induce thermal fission. This separation between moderator and fuel prevents neutrons from being captured in resonances through radiative absorption reactions in uranium during the moderation processes.

[0005] In the multiplication factor formula K, where a simplified K is penf, where one of the four factors is the parameter p, known as the escape probability of Petition 870260065452, dated 03 / 07 / 2026, page 7 / 54 / 46 resonance. In turn, the effective multiplication factor kef considers the escape through the outer periphery of fast and thermal energy neutrons. This fact only shows that the resonances of the fuel elements are detrimental to the criticality of the reactor core and its operation. Therefore, the reactor core design allows for the escape of neutrons from fuel resonances, meeting a high p-factor.

[0006] Reactors produce a neutron flux with a spectrum similar to the Maxwell-Boltzmann distribution covering a wide energy range, from 0.01 eV to 14 MeV. These neutrons arise from fission reactions and, once moderated, exhibit continuous, isotropic, diffusive fluxes in the broad thermal, epithermal, and fast energy domains.

[0007] Depending on the reactor core type, either thermal or fast spectra may predominate without limitation. Neutron fluence within a critical or subcritical reactor core exposes all nuclides of the internal constituent materials. Consequently, reaction rates are proportional to neutron fluence, the atomic densities of the elements, and the various microscopic cross-sections (XS) associated with all interactions within its components and materials. In general, there is no technology capable of selectively limiting neutron spectrum interactions with materials in reactor cores. In fact, there is no core that operates predominantly or preferentially covering a resonance neutron spectrum.

[0008] Therefore, reactor cores generate a high concentration of radioactive contaminants, along with short- and long-lived fission products, which accumulate throughout the fuel burnup cycle. Furthermore, there are temporary burnt-out poisons that hinder the maintenance of reactor criticality. To maintain the delicate stability of criticality (unit kef) throughout the fuel cycle and neutralize the accumulation of undesirable nuclides, the core composition must incorporate abundantly enriched fissile elements and pre-installed additional absorbers. The design of these absorbers allows for constant criticality with stable fuel consumption during the burnup cycle, thus ensuring the necessary balance. Petition 870260065452, dated 03 / 07 / 2026, page 8 / 54 / 46

[0009] Reactor cores operate with fissile elements such as U233 and U235. In thermal reactors, uranium fuels generally have a U235 isotopic enrichment level of 3-5%, which is higher than the natural abundance of 0.7%. An example of this fuel is found in PWR (Pressurized Water Reactor) reactors.

[0010] Reactors can be regenerative, capable of transforming fertile elements into fissile elements. However, to do this, they require a high neutron production to support the criticality of the core and provide excess neutrons for the conversion of Th-232 to U-233 or U-238 to Pu-239. This conversion occurs at the periphery of the core, in regions called "covers." These are made of fertile elements that capture neutrons escaping through the periphery. However, these reactors support criticality (unit kef) using enriched U-235. The converted fissile elements can burn up in other reactors after reprocessing.

[0011] Reactor cores maintain a significant inventory of fissile elements, which burn throughout the cycle of a typical fuel, generally lasting three years, maintaining a stable kef criticality during the cycle. Sudden instability can lead to subcriticality, resulting in unit shutdown, or to supercriticality, which can potentially cause nuclear accidents, releasing fission products produced and stored in the core as occurred at the Chernobyl Nuclear Power Plant, resulting in lasting environmental damage.

[0012] The temporal dynamics of kef, in response to changes in nuclide concentrations within the reactor core, can be extremely rapid, occurring in fractions of a second. This represents a challenge for safety systems in nuclear power plants, as it presents an inherent risk to current nuclear systems.

[0013] In “Analysis of the Nuclear Reactor” by Duderstadt, James J. and Hamilton, Louis J. (John Wiley & Sons, Inc., Michigan, 1976), the authors provide a comprehensive description of the nuclear interactions between the elements and the neutron spectrum found in reactor cores. This literature provides a body of knowledge in the area of ​​reactors and adds to the experience in the field of nuclear reactor engineering. Summary of the Invention Petition 870260065452, dated 03 / 07 / 2026, page 9 / 54 / 46

[0014] The present invention describes equipment, called Multiplicative Fission Converter Core - MFCC, which is a nuclear unit equivalent to a reactor core that supports, in controlled and continuous operation, the nuclear fission reaction and conversion of fertile elements.

[0015] The primary components of the MFCC are modulators consisting of solid cylindrical halos with diameters R. These halos rotate at an angular velocity w to alter the neutron energy spectrum emitted by an internal source. The modulators replicate distinct normal distributions of neutrons on the peripheral surface, characterized by an average energy Em and a standard deviation σ. These distributions optimize the reaction rate by meeting the fission cross-section (XS) requirements of fissile elements and the radiative capture cross-section (π,γ) requirements of the fertile element at different spatial positions.

[0016] The MFCC operates on the Th232-U238 cycle, in which the fertile element Th232 is converted into fissile material and then transferred to the unit responsible for the fission of the generated fissile products.

[0017] The MFCC can also function in the U238-Am243 cycle, in which the fertile element U238 is converted into U239 and subsequent isotopes, which decay into Pa isotopes and then into U233 and U235, and so on. These isotopes feed the unit responsible for conducting the fission reaction of the generated fissile products.

[0018] The MFCC has a conversion module - MC (1), one or more multiplicative fission modules - MF (2), and a pulsed neutron source module - MS (4), supporting radial symmetry.

[0019] The MFCC is an invention that allows radiative capture reactions to occur in fertile nuclides such as Th-232 or U-238 within the conversion chamber CC (11), transforming them into fissile materials that then proceed to the fission chambers CFs (16, 17) where continuous fission occurs.

[0020] The MFCC directs and adjusts the neutron energy from a pulsed FP source (20), generating characteristic spectra optimized to sustain multiplicative fission. It sequentially amplifies the neutron fluence while directing it towards the conversion of fertile elements into fissile ones. Petition 870260065452, dated 03 / 07 / 2026, page 10 / 54 / 46

[0021] Conversion rate optimization occurs by favoring nuclear radiative capture reactions (η,γ) of the fertile element in the CC(11) chamber by adjusting the average neutron distribution energy to a nuclear resonance spectrum. In CFs, fission (n,f) occurs with an average neutron distribution energy adjusted to the extremely low energy range in cold neutrons or fission resonance energies, promoting fissile reactions in nuclides with high XS behavior of 1 / v cross-section at low energy or in the resonance spectrum. This reduces absorption rates in regions outside the XS spectrum for the isotopes present and other nuclides with different XS behavior. Technical Problem

[0022] Light water reactor (LWR) cores maintain enriched U235 to achieve criticality at a sufficient level throughout the burn-up cycle. Pre-installed absorber rods in the reactor core compensate for excess fissile material at the start of the cycle.

[0023] The nuclear industry must enrich natural uranium by increasing the isotopic abundance of U-235 in fuel rods. This preprocessing procedure is expensive and technologically sophisticated and, along with fuel reprocessing, contributes to the proliferation of nuclear weapons.

[0024] There are no reactor cores that operate solely on fertile elements, such as Th232 or U238, without the presence of U-235 or Pu-240 enriched beyond natural levels, when cooled and moderated by light water. Furthermore, in each cycle, typically lasting three years, fresh fuel replaces the fissile elements in combustion.

[0025] Thorium, which is four times more abundant in nature than uranium, holds untapped energy potential. However, the transmutation of Th-232(n^) with subsequent production of fissile isotopes of Pa and U in nuclear reactors is still under investigation for breeder reactor types, and has not yet seen widespread commercial application.

[0026] The disadvantage of nuclear technology lies in the accumulation of fission products generated by nuclear reactors, which increases with the combustion cycle and mixes inside the ceramic fuel itself. The radiation and heat from these Petition 870260065452, dated 03 / 07 / 2026, page 11 / 54 / 46 fission products initially stored in nuclear power plants make the system radiologically unsafe. The safety of nuclear reactors is in question due to the nuclear accidents at Three Mile Island (USA), Chernobyl (former USSR) and Fukushima (Japan), which caused serious damage to the populations around the plants and to the environment. As an example, Germany, which had a robust nuclear program, chose to shut down all its nuclear reactors and now relies heavily on gas for heating.

[0027] The reactor core retains irradiated fuel, containing U235 and Pu239, transuranic elements, and fission products (FP), during the fissile element burnup cycle. These contaminants are subsequently transferred to the reactor pools with each cycle. It is impossible to separate, segregate, or reuse the fuel during the cycle.

[0028] The decommissioning of a nuclear power plant is a complex and expensive process for which countries still lack experience. Due to the accumulation of radioactive waste in the facilities, there is high radiological contamination of the plant's mechanical systems, and the methods of dismantling and disposal are still uncertain. (IAEA Safety Standards Series No. SGS-40; IAEA-TECDOC-1755)

[0029] Nuclear energy production in thermal or fast reactors generates radioactive waste, regardless of the fuel cycle or burn time, using any current technology. The reactor core accumulates this mixed waste within the fuel rod. Solution to the problem

[0030] The proposed innovative technology modulates the energy spectrum and angular direction of neutrons, spatially limiting them within the nuclear system. This invention exposes a portion of the cross-sections (XS) of fertile elements to undergo radiative capture (η,γ) in a specific chamber, while exposing fissile elements to fission (n,f) in another limited energy spectrum within a distinct chamber. This allows for controlled and restricted interactions with their target nuclides in distinct spatial regions and specific energy spectra.

[0031] This technology works in a unique way, prioritizing spectral regions that favor nuclear resonances for fission in fissile elements and transmutation. Petition 870260065452, dated 03 / 07 / 2026, page 12 / 54 / 46 radioactive in fertile elements. The neutron energy in this equipment selectively directs and exploits these resonances in a controlled manner, instead of escaping them, as occurs in the cores of traditional reactors.

[0032] The solution to this problem is achieved through a combination of premoderators and rotating modulators with specific angular velocities and diameters. These components adjust and optimize the production of selective neutron spectra, allowing them to react with each target nuclide present in specific spatial regions. Nuclides outside this spectrum or spatial region become inert in terms of transmutation and fission, reducing the contamination generated.

[0033] Furthermore, the MFCC produces its own fissile elements through the continuous conversion of fertile elements. During operation, the MFCC converts fertile material into fissile material and facilitates fission in sufficient quantities without accumulating fissile elements within the module. Therefore, there is no need to add fissile elements during operation; the MFCC produces its own fissile material.

[0034] The MFCC also allows for the presence of a multiplicative factor kef in the fission chambers, where fission occurs. The criticality dynamics within these chambers are inherently slow, governed by the production time of fissile elements, which typically takes hours to days. This production is naturally controlled by radioactive decay half-lives, such as Th-233 -> Pa-233 -> U-233 and Th-234 -> Pa234 -> U-234 in the Thorium cycle, or U-239 -> Np-239 -> Pu-239 and U-240 -> Np-240 -> Pu240 in the Uranium cycle, among others, present in the conversion of fertile elements to fissile elements.

[0035] The MFCC operates with fertile elements that, when in concentration equilibrium, do not require the addition of enriched fissile elements for continued operation, as it generates its own fissile fuel. Furthermore, the MFCC does not accumulate fission products. When coupled to a complementary RSS system in patent application process (PCT / BR2023 / 050225, Date Received: July 1, 2023, Receiving Office: National Institute of Industrial Property (Brazil)) WIPO), the MFCC can continuously treat its own radioactive waste, which consists of PF fission products. Petition 870260065452, dated 03 / 07 / 2026, page 13 / 54 / 46

[0036] The MFCC, in terms of geometry, components, material composition and operation, differs significantly from current nuclear reactor core technologies. In the MFCC, the coolant circuit is completely separated from the fuel fluid. The fuel fluid contains only consumable fissile nuclides and their fission products, whose PF can be removed and decontaminated online in the RSS system.

[0037] This patent represents a shift in the basic assumptions of nuclear technological development, resolving serious safety, radiological and environmental issues associated with the nuclear industry. Advantageous effects of the invention

[0038] MFCC is a modular piece of equipment with separate physical and functional parts that are replicable. As a result, both the installation and decommissioning of parts become easy to perform, and parts can be swapped during the operating process.

[0039] After reaching equilibrium in the atomic concentrations of nuclides generated over time, the MFCC begins to convert fertile elements (X) into fissile elements (Y) that are self-produced and consumed as long as and if fertile elements are present and the pulsed source module is generating neutrons.

[0040] The MFCC, in equilibrium of fissile nuclide concentrations in the fission chambers, operates only with natural Th232 or U238, without additional isotopic enrichment. This unique condition is achieved by producing neutron distributions with an average energy adapted to the highest cross-section value XS (n,f) of fissile nuclides and XS (η,γ) of fertile nuclides. This intensification of the nuclear system response effectively reduces the need for enrichment of fissile elements in the nuclear system.

[0041] To reduce the time required to reach equilibrium of fertile-fissile concentrations, it is possible to introduce fissile elements to initiate the operation of the MFCC, which begins close to equilibrium of fertile-fissile concentrations.

[0042] The MFCC operates in optimized selective neutron spectra within the resonance range, minimizing the generation of more radioactive contaminants beyond the final fission products. Petition 870260065452, dated 03 / 07 / 2026, page 14 / 54 / 46

[0043] The MFCC, combined with the RSS configuration arrangement (patent submission PCT / BR2023 / 050225, Date Received: July 1, 2023, Receiving Office: National Institute of Industrial Property Brazil), represents a new type of nuclear system for nuclear energy production, where the self-conversion of fertile elements into fissile elements, the consumption of fissile elements, and the burning of radioactive waste occur through MFCC and complementary RSS units.

[0044] The multiplicative effect that occurs in the fission chambers CFs (16, 17) can be amplified by increasing the number of fission modules - MF, adjusting the thickness of the static moderators in contact with the CFs, increasing the intensity of the pulsed source - FP, and extending the residence time of the fluid with fissile elements in the passage through the CFs.

[0045] The long natural conversion time of fertile elements into fissile elements, characterized by the β decay half-lives of the nuclides Th233, Th234, Pa233, Pa234; or U239, U240, Np239, Np240, limits and delays the dynamics of the multiplicative factor kef.

[0046] The technology is not proliferative, as it produces and consumes the fissile nuclides generated and reduces the production of transuranic compounds.

[0047] The MFCC invention operates at equilibrium concentrations of fissile fertile nuclides, whether under subcritical or critical conditions. It enables the generation of heat and, consequently, thermoelectric energy through nuclear fission using fertile elements such as Th-232 or natural or depleted uranium. This technology does not require enrichment with fissile elements due to its optimized capacity for self-conversion of fertile elements and fission of the converted products. Brief description of the drawings

[0048] Figure 1 shows the constituent modules of the MFCC, namely: (A) Conversion Module - MC(1), Fission Module - MF(2) and Source Module - MS(4); and (B) provides details of the MC constituents.

[0049] Figure 2 illustrates the components of the MF, showing (A) the possible repetitions of MF (2, 18) and (B) the two options for the components of MF (2) {MK(5), CF(16), MB(13)} and {MK (5), CF(16), MR(14), PMB(24)}. Petition 870260065452, dated 03 / 07 / 2026, p. 15 / 54 / 46

[0050] Figure 3 illustrates the MFCC1 arrangement with modules {MC(2), MF(2), MS(4)} comprising a single unit, with CC(11) and CF(16) cameras interleaved.

[0051] Figure 4 illustrates the MFCC2 arrangement following a condition of modules {MC(1), MS(4)} and {MF(2), MS(4)} operating independently in parallel, with fluid crossing (8) from CC(11) to CF(16).

[0052] Figure 5 illustrates MFCC3 in a special condition where there is a single module M, assuming the conversion operation MC(1) or fission MF(2), depending on the rotation values ​​wnem different operating times OT, T1 and T2.

[0053] Figure 6 illustrates a transport diagram of the flows of a collector fluid, from the inlet (46) to the outlet (59), the cooling fluid flows in chambers CC(11) and CF(16), including heat exchangers and working fluid FdT.

[0054] Figure 7 illustrates a flow diagram of fresh Fd (without residues) and contaminated FdC collector fluids (35) and cooling fluids (31, 32, 33) between the MFCC and the CPM chemical processing module (39), the heat exchangers (HEs) and the TB turbine.

[0055] Figure 8 illustrates a 3D side view of MFCC1 representing the main external components.

[0056] Figure 9 illustrates the collector tube rings (47), the coolant (49) for the CC(11) and CF(16) chambers and the coolant (44) for the throttle target, including heat exchangers, all included in the MFCC1.

[0057] Figure 10 describes separately (A) the collector fluid circuit Cc (6) and (B, C) the refrigerant fluid circuits HCa, HCcc, HCc.

[0058] Figure 11 illustrates the upper, side and base supports of the MFCC1 representation, including the positions of the speed motor.

[0059] Figure 12 illustrates the time-dependent variations in atomic densities of fertile and conversion products for MFCC operation in the (a) Th232 and (b) U238 cycles.

[0060] Figure 13 shows the generation of thermal energy as a function of operating time for a specific MFCC operating in cycles (a) Th232 and (b) U238, describing the Petition 870260065452, dated 03 / 07 / 2026, page 16 / 54 / 46 transition from obtaining the equilibrium concentration following the continuous operation time.

[0061] Figure 14 shows (A) Em of Dn(Em, σ) taken at discrete radial intervals, and (B) Em of Dn(Em, σ) up to 100 groups, representing 1 and 4 cases, both as a function of the interval R.

[0062] Figure 15 shows the MRI project data with graphite and zirconium alloys. Description of the Invention

[0063] In MFCC equipment, the following modules stand out: the conversion module MC (1), the fission module MF (2) and the source module MS (4). In this configuration, the source FT (20) generates a neutron distribution in the MS module (4) and diffuses it to the MF module (2) to adjust the average energy of the distribution to the desired energy of the fission cross-section (XS). MF (2) promotes fission by generating fission neutrons (NF). The MF module (2) amplifies the neutron distribution and transports it to the MC module (1). MC (1) adjusts the neutron distribution energy for the XS(n,Y) conversion of fertile nuclides in the MX matrix (3) within MC (1).

[0064] Figure 1(A) illustrates the arrangement {MS (4), MF (2), MC(MX) (1)} of the MFCC modules, coil MFCC1. In MFCC1, there is a neutron flow in the radial direction, while there is a mass flow (6) of nuclides in the opposite direction.

[0065] Figure 1(B) illustrates the sequential components {PMB (24), MR (14), CC(MX) (11) and RF (10)} that make up the MC module (1). The neutrons pass from PMB (24) to MR (14) and then to CC (11), reaching MX (3) contained in the CC chamber (11).

[0066] The MX (3) material matrix, internal to CC (11), is composed exclusively of fertile elements, which, when exposed to neutrons in a selective spectrum, undergo conversion from fertile nuclides to fissile nuclides.

[0067] In detail, MC (1) is the conversion module composed of the following components: a low-energy dynamic pre-moderator - PMB (24), a dynamic modulator known as a resonance modulator - MR (14), a conversion chamber - CC (11) containing internally a matrix of fertile nuclides (MX) (3), followed at the periphery by a neutron reflector - RF (10). Petition 870260065452, dated 03 / 07 / 2026, page 17 / 54 / 46

[0068] In turn, the multiplicative fission module - MF (2) can appear as a single unit or in repetition in multiple units (2 and / or 18). The MF is composed of the following components: static pre-moderator - MK (5), fission chamber - CF (16), followed by one of the options: low energy modulator - MB (13), or the pair PMB (24) and MR (14).

[0069] Figure 2(A) illustrates the possibilities of repeating MF (2, 18), including multiple FC chambers, CF1 (16) and CF2 (17).

[0070] Figure 2(B) illustrates the two options for MF composition (2), keeping {MK (5), CF(16)} followed by {MB (13)} or {MR (14), PMB (24)}, to address distinct energy spectra of the XS cross section.

[0071] MB (27) generates a neutron distribution with an average energy Em in the cold neutron range from 0 to 25 meV, represented here as close to 1 meV. Meanwhile, the pair {MR (14), PMB (24)} generates a neutron distribution with an average energy Em close to the resonance energy Eo present in the XS cross-section of the fissile nuclide (Em ~ Eo). The choice depends on which region of the energy spectrum of the fissile nuclide fission XS in CFs will be prioritized, i.e., cold neutron energy or resonance energy.

[0072] MK (5) is a static moderator, which, in contact with the fission chamber CF (16 or 17) filled with fissile elements, forms a {moderator-fissile nuclides} set that helps to increase the fission rate, maintaining a multiplication factor kef.

[0073] MFCC maintains a neutron reaction and transport triad starting with the MS module (4) of pulsed neutron emission ion-nucleon reactions, fissile reactions in CF (16 or 17) with multiplication in MK(5) / CF(16,17) within MF (2), followed by fertile nuclide conversion reactions in the MC module (1).

[0074] In the pulsed neutron emission module MS (4), the source (20) generates neutrons that diffuse into a pre-moderator PM (15) and are directed radially towards the MF (2 and / or 18).

[0075] It is known that in static moderators, fast neutrons undergo passive diffusion with a predominance of "downscattering" (scattering with energy loss relative to a fixed reference frame), reaching thermalization. On the other hand, when moderation occurs within dynamic materials, i.e., target nuclei moving at high speeds Petition 870260065452, dated 03 / 07 / 2026, page 18 / 54 / 46 radial velocities, the authors define the possibility of active diffusion, where neutrons can undergo rapid “downscattering” in the central region and prolonged “upscattering” (scattering with energy gain relative to a fixed reference frame) predominantly near the periphery, with the neutron velocity being adjusted to the velocity of the nuclei in the medium and being transported to the periphery of the moderator. Thus, the pair of variables radius R and angular velocity wn can define the terminal velocity of the neutron and, consequently, the energy of interest, since E is proportional to (wn. R)2.

[0076] In MF(2), neutron energies adjust to the desired levels for nuclear fission in CF (16 or 17). This allows them to hold energy in the cold neutron range using the low-energy modulator MB (13) or in the fission resonance energies by PMB (24) and MR (14).

[0077] In MF (2) and (18), neutrons undergo fission within the fission chambers CF1 (16) and CF2 (17), generating neutrons in the fission spectrum. In CFs(16,17), these neutrons multiply due to the presence of fissile nuclides and the static moderator MK(5). Due to the reduced thickness of MK (5), the neutrons escape radially towards the periphery. In CFs, the fission reactions produce heat Q and fission products (PF).

[0078] Therefore, neutrons from the FT source move radially from FT to MF, multiplied in the MK (5)-CF (16 or 17) system and then transported to the periphery in MC (1). It is important to emphasize that radial transport is not due to passive diffusion, but rather active, aided by the rotation of the MB (13), MR (14) and PMB (24) modulators present in the MFCC system.

[0079] In the opposite direction, from the periphery to the central axis (21), there is mass transport (6) between the CC (11) and CF (16, 17) chambers, directed from MC (1) to MF (2), transporting converted fertile elements (Y) in CC (11) to the fission site CF (16, 17). A fluid, called the collector fluid Fd (6), passes through MC (1) removing the converted fissile elements in the MX (3) matrix and transporting them from the CC chamber (11) to the fission chamber CF (16) in the fission module MF (2).

[0080] The arrangement of MC(1) and MF(2) can be different. Thus, the MFCC presents these modules in one of the following groupings: MC(1) and MF(2) as dependent modules forming a single unit {MC(1), MF(2), MFCC1 coil arrangement} Petition 870260065452, dated 03 / 07 / 2026, p. 19 / 54 / 46 MS(4)}, and as independent modules {MC(1), MS(4)} and {MF(2), MS(4)} forming two units, namely, arrangement MFCC2; and operating continuously over time.

[0081] Figure 3 illustrates the MFCC1 arrangement, with {MC(1),MF(2),MS(4)}, where the components maintain the same central axial axis (21), placed in series, forming a single unit.

[0082] Figure 4 illustrates MFCC2 consisting of the pair of components {MC(1), MS(4)} and {MF(2), MS(4)}, forming two separate independent units. The first unit generates fissile nuclides Y by converting X fertile elements by XS (n, γ). The second unit is a firing unit that occurs by fission reaction in fissile nuclides Y in the CF of type Y(n,f).

[0083] Figure 5 illustrates a special condition for MFCC3. In this case, MFCC3 can also exist as a single unit M, which functions as MC(1) for a given period T1 and subsequently as MF(2) for a subsequent period T2. Such an arrangement is represented by MFCC3. This arrangement can also burn any type of nuclides by other reactions, such as (n,a), (n,p), or (n,d) which have high XS absorption of the (n, nucleon) type with low energy 1 / va XS behavior in cold neutron spectra.

[0084] Therefore, there are three arrangements MFCC1, MFCC2 and MFCC3, according to the distribution of the MC, MF and MS modules. If not specified, the MFCC description applies to all three schemes.

[0085] MFCC contains a conversion chamber - CC (11). An MX (3) matrix of fertile cores is contained inside the CC (11). The MX (3) material consists of natural solid elements Th or U fertile X not enriched, in metal, carbide XC2, or oxide XO2 chemical form, not limiting.

[0086] The fission chambers CF1 or CF2 (16, 17) perform fission reactions (n,f) on fissile solute nuclides Y in collecting fluid (6). There is a compartment (28) in CF(16,17) to receive such fissile nuclides in Y from the CC (11). Inside the CFs, there is also a matrix MY (77) of fissile material. Thus, R(n,f) reactions can occur in Y in solute and in solid matrix MY (77). The MY (77) helps to initiate the operation of the MFCC, at the time when the appropriate concentration of solute Y is not attainable due to the lack of equilibrium of nuclide concentrations. Petition 870260065452, dated 03 / 07 / 2026, page 20 / 54 / 46

[0087] MFCC can have only one fission chamber CF1 (16) or multiple chambers, CF1 and CF2 (16 and 17), through repetitions of {CF, MF(2)}, where MF(2) can contain {MB(13)} or the pair {MR(14), PMB(24)}.

[0088] MS (4) contains a pulsed source (20), a static pre-moderator PM (15) and the neutron reflector (10).

[0089] The MR modulator (14) maintains a magnetic connection with the rotor of a second electric motor via the shaft (23), while the other low-speed halos MB (13) and PMB (24) are directly connected to the shaft (23) and the motor rotor (66).

[0090] PMB (24) and MB (13) operate by reducing the speed of neutrons to low energies, preferably through the “downscattering” process in MB(13) and PMB(24). Both are rotating at low angular speeds, ~105rpm, which can be adjusted. MB (13) operates by reducing the energy of neutrons to cold energies, ~0.001 eV; while PMB partially performs this function, supporting the average energy close to the epithermal range (~1 eV).

[0091] The MFCC supports at least two distinct types of nuclear reactions. One occurs in the conversion chamber CC (11), adjusting neutron energy to achieve resonance energies in the fertile element of the internal array MX (3) within the CC chamber (11). The second type of reaction occurs in the fission chamber CF1 and / or CF2 (16-17), inducing fission by cold neutrons from a modulator MB (13). Thus, pulsed source neutrons (20), pre-moderated (15), are cooled in MB (13) and induce fission in the target of the fission chamber CF1 (16 and 17, respectively).

[0092] The fast neutrons generated in the fission of fissile Y nuclei present in the fission chamber CF1 (16) or CF2 (17) proceed to the moderating halo MK (5), where thermal multiplication can occur. These neutrons are then actively diffused to PMB (24) and then to the resonant modulator MR (14), adjusting the neutron energy to the resonance energy of the cross-section (η,γ) of the fertile X nucleus. The X nuclei in MX (3) within the conversion chamber CC (11) are the target of the neutron distribution of MR (14).

[0093] In another choice, MFCC operates fission in the fission chamber compartment CF1 (16) at resonances in the XS (n,f) shock section with fission amplification in Petition 870260065452, dated 03 / 07 / 2026, page 21 / 54 / 46 MK (5). In this case, instead of having an MB modulator (13) after PM (15), there is also a PMB pre-moderator (24) followed by an MR modulator (14).

[0094] When fission occurs in a fission chamber CF1 (n-1), fast neutrons Nf are generated. This neutron distribution can be moderated and its average energy adjusted to the resonance energy (XS with well-defined resonance) or to the thermal energies (XS with low energy 1 / va behavior). Thus, the neutrons generated in CF (n-1) feed a second chamber, CF2 (n). This process can be repeated (n, n-1, n-2, ...etc). Due to the presence of a static moderator MK(5) near the fission chamber, primary source neutron multiplication (20) can occur, allowing the determination of a multiplication factor for the n MF modulus, which is characteristic of the material, geometric and quantitative conditions of fissile and fertile materials present in the MFCC.

[0095] Table 1 illustrates the nuclear characteristics of the nuclides (Z, N) and the radiative capture and radioactive decay (β-) processes from Th-232 to U238, in a simplified manner. Th232 is the fertile X element, a precursor to the multiplicative fission process. U238 was assumed to limit the process due to its low fission (n,f) or radiative capture (π,γ) reactions in the cold neutron spectrum and low concentration generated in the fission chambers (FC). The spectrum is selective; for example, there is a significant cross-section (η,γ) of 1000 b for an Eo of 5.5 eV of U236. However, if the spectrum is limited to cold neutrons ~1 meV in the FC1 and FC2 chambers, there will be minimal interaction at this resonance energy of U236.

[0096] The conversion of Th232 in MX (3) to Th233 occurs via the R(n^) reaction at the resonance Eo of 23.4 eV or 21.8 eV, with a cross-section of 2750b or 1790b, respectively. The MR modulator (14) produces on its output face a representative neutron distribution equivalent to a Normal distribution of neutrons Dn(Eo, σ) covering the energy range Eo ± σ, with Em ~ Eo. Thus, MR (14) favors the conversion reaction R(n^) Th232(n, Y)Th233 at the resonance energy Eo. In fact, the (n,f) or (n,Y) fission reactions in the 1 / v behavior in DC become impossible, due to the selectivity of the specific neutron spectrum produced in DC (11).

[0097] If the fertile nuclide X present in the MX matrix (3) is Th232 in CC (11), the conversion Th232(n,Y)Th233 will occur, followed by decays and other radiative captures such as Th233^-)Pa233, Th233(n,Y)Th234, Th233^-)Pa-233, among other transformations. The Petition 870260065452, dated 03 / 07 / 2026, page 22 / 54 / 46 nuclides Pa and U are removed from the MX matrix (3) by elution, extracting through the collecting fluid Fd (6) which transports these nuclides to the fission chamber CF1 (16). The collecting fluid Fd (6) continues to transport the fissile Y nuclides from the first fission chamber CF1 (16) to the subsequent ones, when there is more than one CF chamber.

[0098] In CC (11) and CFs (16, 17), radioactive nuclides continue to undergo radioactive decay and radiative capture reactions (η,γ). The R(n,Y) and R(n,f) reactions can continue to occur in CF if exposed to cold neutrons and if the precursors have high cross sections in the cold neutron spectrum. In this context, if the fertile nuclide X is Th232, there will be reactions such as Th233(n,Y)Th234, Th233(p-)Pa233, Pa233(n,Y)P-234, Pa234(e-)U234, Pa233(e-)U233, U233(n,Y)U234, U234(n,Y)U235, among others. If two CF chambers are used, the increase in the concentration of these Y nuclides in each chamber can be evaluated in the process.

[0099] The consumption of fissile elements will occur through fission by cold neutrons in the CF1 (16) and CF2 (17) chambers. In the case of Th232 in MX (3), the CF chambers will contain U233, U234, U235, Pa233, Pa234, exposed to cold neutrons from the MB modulator (13). Therefore, fission does not occur in just one fissile nuclide, but in all precursors Y of the fertile element X, even if they have short half-lives.

[0100] In summary, conversion processes by (n,Y) reactions occur in the resonant range in DC, and by fission in (n,f) reactions in CFs within the cold neutron range, respectively. This process provides R(n,Y) resonance in DC(11) and R(n,f) in CF(16) for cold neutrons. However, it is also possible to have R(n,Y) in DC(11) and R(n,f) in CF(16) following resonance spectra.

[0101] Table 2 identifies the nuclear characteristics of the X(Z,N) nuclides and the radiative capture and radioactive decay (β-) processes, from U238 to Am243, in a simplified manner. In this case, U-238 is the fertile X element in MX (3), a precursor of the multiplicative fission process. Pu242 is defined as the limiting nuclide due to its low fission cross-section (n,f) of 0.05 b and low (n,Y) cross-section of 100 b compared to other Pu, Np, and U nuclides in the cold neutron spectrum. There is a significant cross-section of Pu242(n,Y) of 100 b a 1 meV; however, it is ten times smaller compared to the equivalent (n,Y) and (n,f) cross-sections of other Y nuclides in the process. Petition 870260065452, dated 03 / 07 / 2026, page 23 / 54 / 46

[0102] The time factor and residence time in the chambers can also help to limit the nuclides (X, Z) in the fission process in CF(16). Thus, with a reduced time and a spectrum limited to cold neutrons (~1 meV), there will be reduced interaction in Pu-242, compared to nuclides from U238 to Am243.

[0103] The conversion of U238 to U239 occurs via the R(n,Y) reaction at the resonance Eo of 6.7 eV, with a cross-section of 7200 b. If MR (14) generates the distribution with Em~ 6.7 eV, the neutrons will follow a Normal Distribution Dn(Em^) in this energy range Eo±σ, where σ is the standard deviation of the particle distribution generated by MR (14). Under this condition, cold neutrons will not be produced, preventing fission or radiative capture reactions (π,γ) with cross-sections in the behavior of 1 / v in CC(11).

[0104] After conversion of U238 to U239, and through transport of Y by the collector fluid, Y is transported to CF1(16), where the fission chamber is exposed to cold neutrons from modulator MB (13). Therefore, in CF (16), radioactive capture and fission processes with significant cross sections (π,υ) and (n,f) in the cold neutron range are favored, complemented by transmutations that occur through radioactive decay. In this context, there are the decays U239(n,Y)U240, U239(p-)Np239, U240(p-)Np240, Np239(n,Y)Np240, Np-239(p-)Pu-239, Np240(p)Pu240, Pu239(n,Y)Pu240, Pu240(n,Y)Pu241, Pu241(n,Y)Pu242, Pu242(n,Y)Pu243, Pu243(p-)Am243.

[0105] In the case of two CF chambers (CF1, 16, and CF2, 17), the concentration of such nuclides in each chamber can be evaluated over time. The consumption of fissile Y nuclides will occur through cold neutron fission in CF1(16) and / or CF2(17), involving U-239, Np239, Np240, Pu239, Pu240, Pu241, among others.

[0106] In addition, the MFCC has the following main components: support structure (68, 69, 70), peripheral static reflector RF (10), central axis (21), solid cylindrical halos. These halos are, namely, the static pre-moderator PM (15); dynamic modulators PMB (24), MB (13) and MR (14), with MR (14) suspended by magnetic edge rings (75, 76). In addition, MFCC has a conversion chamber CC (11) with an MX matrix (3), fissile chambers CFs (16, 17), containing fissile nuclides Y in solution, and can also have Y in a solid matrix MY (77). Petition 870260065452, dated 03 / 07 / 2026, page 24 / 54 / 46

[0107] The concentric cylindrical halos (5, 10, 13, 14, 15, 18, 24) are situated around the central axis (21), alternating between the CC chambers (11) and CFs (16, 17). MF (2) is just a solid rotating ring MB (13), or the rotating concentric rings PMB (24) and MR (14), always placed in sequence with CF (16) and MK (5).

[0108] Each dynamic cylindrical halo allows a nominal angular rotation wn, whose rotation axes (22 and 23) are in the axial direction, accommodating arbitrary angular velocities. The dynamic modulators and pre-modulators interconnect with the electromechanical system, positioned at the bottom.

[0109] PM (15) and MK (5) are static. On the other hand, the halos for PMB (24) and MB (13) operate at low speed and do not require levitation. The halo for MR (14) runs at medium and high angular speed, and magnetic levitation is of interest to reduce friction.

[0110] The static Pre-Moderator (PM) (15) houses the pulsed neutron source (20). PM (15) produces partial thermal moderation of neutrons limited to passive neutron diffusion up to the outer Rpm radius of PM. The pre-moderation alters the fast emission spectrum of fission neutrons, such as Watts or Maxwell-Boltzmann (~keV to MeV) at high energies, to a sub-thermalized spectrum, with partially isotropic diffuse angular orientation escaping at the periphery of the PM cylinder (15).

[0111] The static PM Pre-Moderator (15) maintains a radial axial hole (19), with neutron sources FP (20) - inserted internally, positioned at half the axial height of the MFCC.

[0112] The static pre-moderator PM (15) is firmly attached to the upper part of the upper support structure. At the lower end of the cylinder, there is a protrusion along the edges, forming a chamber for coolant (12). This capsule (12) is used to assist in side cooling, especially if MB modulator (13) is used.

[0113] PM (15) is made of low Z material (H, D, F, C, O), however, with insufficient Rpm radius for fully moderated neutrons at thermal energies. Therefore, the neutrons are said to be pre-moderated as they are transported to the inner surface of the MF module (13), which will adjust the average of the neutron distribution energies through dynamic diffusion to the required energy level. Petition 870260065452, dated 03 / 07 / 2026, p. 25 / 54 / 46

[0114] The static moderator MK (5) partially thermalizes the neutrons generated in fission within the CF, contributing to the kef multiplication factor. MK (5) is a static cylindrical halo made of moderator material composed of light elements such as H, D, C and Be. In MK (5), the “downscattering” of fast fission neutrons occurs preferentially.

[0115] The Low-Velocity Dynamic Premodulator (PMB) (24) moderates fast neutrons to epithermal energies (~1eV), preferably through “downscattering”, reducing the fast neutron energies. The PMB initiates the modulation process of the angular direction of the neutrons. PMB (24) is made of low Z elements, such as H, C, D, F, Be. This premodulator is rotatable and maintains an angular velocity wn equal to or close to the MB modulator (13).

[0116] PMB (24) can introduce additional pre-moderation at the MR (14) modulator input, favoring a radial reduction of R and wn in the MR (14) design. It is of interest to generate a neutron distribution at the MR (14) modulator input with an average energy Em lower than the resonance energy Eo so that the energy evolves radially, since in MR (14) “upscattering” preferentially occurs. In the case of PMB (24) preceding MR (14), the pre-modulator PMB (24) operates in wn and radius RPMB in such a way that the average output energy is close to 0.1 to 1 eV, depending on the resonant energy Eo to be addressed.

[0117] The MB (13) low-energy modulator is a dynamically low-rotation cylindrical halo capable of receiving, at the inner interface, a diffuse isotropic neutron spectrum in a Maxwell-Boltzmann spectrum, close to thermal energies (~ eV) at the output of PM (15) and adjusting the neutron spectrum to very low energies in the cold neutron domain (~1 meV) at the outer interface of MB. This is the average design energy for MB (13), although MB can operate at lower average energies if required.

[0118] MB (13) is typically made with low Z elements of minimum radiative absorption cross-section (XS) and high XS scattering to facilitate rapid “downscattering”, preferably. Common materials for MB (13) include F, C, D, Be and O, among others.

[0119] The MR Resonant Modulator (14) is a dynamic cylindrical halo with high rotation (>105rpm), held in magnetic suspension, capable of receiving at its internal interface a Petition 870260065452, of 03 / 07 / 2026, page 26 / 54 / 46 radially oriented neutron spectrum at low energies (~ 0.02-1.0 eV) from the output of the PMB pre-modulator (24) and fit the spectrum to Dn(Em, σ), with Em close to the resonant energy Eo for the relevant cross-section (XS) in question, where Eo is 23.4 eV or 21.8 eV for Th232, or 6.5 eV for U238 (not limiting, in the process of fitting the resonances of the fertile nuclides and producing Y), at the outer interface of the MR (14).

[0120] MR (14) is made with intermediate Z elements (C, F, Be, Zr, non-limiting). In the outer radius of Rmr, MR (14) provides a neutron output in a radially oriented beam.

[0121] In summary, MR (14) adjusts Dn(EmO) in the resonance energy conforming to a normal distribution and adjusts Em in the resonance energy Eo.

[0122] The peripheral RF reflector (10) is located on the outside, made of a static concentric halo coupled to the lateral support structure (69). This reflector consists of a high elastic scattering cross-section material, with high Z to avoid energy losses in elastic collisions, and a very low neutron absorption cross-section in the spectrum adopted for the target internalized in the DC conversion chamber (11). When the chosen material can also provide moderation to thermal energies, Boron is added to the outer peripheral layer of the reflector to remove any thermal neutrons that may escape. This protection can also exist at the base and top of each PMB (24), MK (5), MB (13) and PM (15) premodulator.

[0123] The pulsed neutron source (20) is at the center of the pre-moderator halo (15), inserted through the halo perforation (19). The neutron source (FP) can generate neutrons through DD or DT fusion reactions, where incident positive or negative D ions come from a deuterium accelerator (9) and are guided (19) to TiD or TiT targets (20) to produce D(d,n) or D(t,n) reactions. Alternatively, the source can produce neutrons through (p,n) reactions using a negative or positive H ion accelerator with energy above the threshold to bombard targets of light chemical elements such as Li, Be or B, positioned in (20). The ratio of neutrons per ion collided with the target depends on various factors, such as the type of reactions p(Li,n), d(D,n), d(T,n) and their cross sections, the target-nuclide atomic concentration, vacuum conditions, and the kinetic energy of the ions. In fact, the ratio varies from 1.10⁻⁶ to 5.10⁻⁴ neutrons per injected ion. Petition 870260065452, dated 03 / 07 / 2026, p. 27 / 54 / 46

[0124] The accelerator injects ions into the guide cylindrical cavity (19), reaching its target (20). Neutron generation occurs with distinct spectra, specific to each nucleon-nucleus reaction and kinetic energy of the incident ions (H-, H+, D+, D-), with energies above the threshold for nuclear reactions.

[0125] These sources (20), as well as ion accelerators (9), are public domain technologies and widely known in academic and industrial fields and will not be described in this document.

[0126] The HCA circulation of a refrigerant fluid whose circuit (43, 44, 55) is accommodated internally within the static cylinder PM (15). HCa cools the target (20) impregnated with T, D, Li, Be or B, recovering the heat after transferring it to a working fluid FdT.

[0127] To better clarify the connection of the shafts (22, 23) of the electromechanical system with the rotating cylindrical halos (13, 14, 24), it is reported that, in the case of low and medium speed rotating cylindrical halos (13, 24), these can be directly connected to the rotor of a motor (65).

[0128] When there are multiple rotating cylindrical halos with different nominal angular velocities wn, it is possible to include an electromechanical system with hollow shaft motors (65, 66) with permanent magnet rotors and stators with coils. Furthermore, variations in angular velocity can be obtained through interconnected gears. This gear technology is known, and detailed connections of the shafts to the modulators 13, 24 and 14 will not be shown.

[0129] The connection of the high angular speed rotary modulators (14) with the motors can be achieved through magnetic interaction, ensuring that there is no mechanical contact and friction between the modulators and their rotating mechanical parts (23). Magnetic bearings are used on the motor shafts (not shown).

[0130] These technologies are well known and widely used, so no specific technical details of this connection are necessary.

[0131] There are four concentric magnetic rings (74, 75) arranged in pairs, one set at the top and the other at the bottom. The magnets are fixed to the top and bottom of the MR modulator (14), and the other set of magnets with the same polarity is fixed to the top and bottom structure of the MFCC. Repulsion is allowed at both the top and bottom, using the same NN and SS poles. At the top of the Petition 870260065452, dated 03 / 07 / 2026, page 28 / 54 / 46 support structure (68), there are metal rings with perforations for positioning magnetic pressure adjustment devices. This adjustment allows vertical positioning of the rotating ring. The asymmetry in the adjustment allows axial and radial adjustment of the MR modulator (14) in levitation.

[0132] The CC component (11) consists of a concentric cylindrical halo, fixed to the lateral structure of the device (69). CC (11) contains internally a solid matrix MX (3), composed of fertile elements, called X(N, Z), which will be converted through radiative capture into fissile material Y(N, Z). CC(11) may be composed of multiple angular sectors.

[0133] In another aspect, a fluid can flow axially on the inner radial side (29) through the inner face of the fertile matrix MX (3). The fissile nuclide Y dissociates from the matrix and can be removed by the collector fluid solution. The solution has a reduced absorption cross-section in the spectrum to which CC (11) is exposed.

[0134] There are two types of chambers: the CC conversion chamber (11), positioned internally to the RF reflector ring (10), and the CF1 fission chambers (16), or additionally CF2 (17).

[0135] Each fission chamber CF (16, 17) is radially tracked towards the periphery by a static concentric ring MK (5), and is radially preceded by MB (13). The components MK (5), CF (16) and MB (13) form the fission module MF (2).

[0136] The CC conversion chamber (11) and CF chambers (16, 17), as well as the MK static moderators (5) and RF reflector (10), can be divided into angled sectors, allowing them to be disassembled and removed without the need to disassemble the entire circuit, or sealed separately, as required for radiological safety.

[0137] Chambers CC (11) and CF (16) contain internally and radially two compartments each, with CC having compartments 26 and 29 and CF having compartments 27 and 28. Peripheral compartments 26 of CC and 27 of CF are used for heat removal through an upward axial flow of a refrigerant fluid.

[0138] The innermost compartments, 29 in CC and 28 in CF, transport the converted fissile nuclides through a fluid flow known as the collection flow (6). The collection flow (6) moves in the inner compartment 29 of CC towards Petition 870260065452, dated 03 / 07 / 2026, page 29 / 54 / 46 upward axial flow, removing converted fissile nuclides from MX (3), and transporting them to compartment 28 of CF (16, 17) following an upward axial flow, where fission can occur.

[0139] The thicknesses of the compartments in CC and CF are different, depending on the residence time of the collection flow. For example, the thickness of CC can be 1 / 5 of the thickness of CF.

[0140] In the inner chambers 28 and 29, on the radial peripheral face, there are solid matrices MX(3) and MY(77) respectively, separating the compartments of chambers CC(11) and CF(16,17). MX (3) is composed of fertile elements X. MY contains fissile elements Y.

[0141] To provide a clearer understanding of the parts of the equipment, a design for MFCC is presented, detailing the transport of HC refrigerant fluids and the collection flow of Fd in its Cc circuit. The complexity of the number of connections in the HC and CC fluid circuits will depend on the number of split angled sectors of the CC chambers (11) and CFs (16, 17).

[0142] Figure 6 illustrates the refrigerant fluid HC (31, 32, 33) transported from the heat generating sources to the heat exchangers.

[0143] The HCa circuit (33) keeps the refrigerant circulating by removing the heat Qa generated in the target (20) due to ion bombardment. HCa has tubes (43) and (44) connected to the cooling capsule (55), inside the PM, and transferring Qa to the heat exchanger (60).

[0144] The heat Qf generated in the fission chamber CF flows through tubes (41) and (42) and is transported to the heat exchanger (61). This cooling circuit is the coil HCcf. There is one HCcf (32) for each CF included in the MFCC.

[0145] In turn, the removal of the heat generated in the conversion of fertile nuclides Qc is from chamber CC (11) and transported through tubes (45) and (46) to the heat exchanger (62). This cooling circuit is HCcc (31). There are HCa, HCcc, HCcf for the MFCC1 and MFCC2 arrangements. There is only one HCc arrangement for MFCC3. Petition 870260065452, dated 03 / 07 / 2026, p. 30 / 54 / 46

[0146] The refrigerant circuits HCs are totally independent. In addition, a working fluid FdT circulates from (63) to (64), removing and transferring the total heat to a turbine or for heating purposes.

[0147] RF (10) and MK (5) are static halos that allow the axial tubes to transfer fluid from the top of the heat exchanger (HEs) to the base of the CC (11) and CF (16) chambers. The refrigerant circulates from the base to the top in cooling compartments 26 and 27 of CC (11) and CF (16), respectively. The same applies to PM (15). Fluids flow in the base rings (50) in CC, (53) in CF, and in the top rings (49) in CC, (54) in CF (16).

[0148] Refrigerants in HC systems can preferably circulate through natural convection by selecting the pipe diameters and the height of the heat source, the height of the heat exchangers, and the variation of density with fluid temperature. However, pumps for forced circulation can be included in-line in each circuit, not shown in the figures.

[0149] Figure 6 also illustrates the transport of the collecting fluid Fd in the Cc circuit (46, 48, 56, 47, 57, 52, 51, 58, 59). This fluid collects the converted Y nuclides in the CC chamber (11), extracting them by elution from the MX matrix (3). Nuclear reactions are known to generate byproducts with kinetic energies thousands of times greater than the chemical bonds of the fertile elements present in the MX matrix (3). Therefore, the converted Y elements are expelled from the matrix of fertile X elements in random directions through various nuclear transformations, and many Y elements can be removed by elution.

[0150] Figure 6 shows that the collecting fluid Fd in the Cc circuit enters (46) and crosses axially the RF (10) to the base ring (48). From there, Fd flows in the axial direction in the compartment (29) where MX (3) is present, collecting the converted Y nuclides and transporting them to the upper ring (47). Thus, the circulation of the fluid Fd occurs radially through (57) tubes from the ring (47) in the upper CC (11) towards the CF (16) down in the MK(5) to the lower ring (52). From there, the Fd flows axially in the inner compartment (28) in the CF (16). Fluid transport can be by natural convection or by an in-line pump.

[0151] The Fd fluid of the Cc circuit, carrying the fissile Y nuclides, exposes these elements in the inner compartment (28) to the neutron distribution Dn that strikes CF (16). Thus, fission will occur, generating fission products PF in Fd. Then, the Petition 870260065452, dated 03 / 07 / 2026, page 31 / 54 / 46 contaminant collector fluid FdC transports PF and Y nuclides from the base ring (52) of CF (16) to the upper ring (54). From there, the FdC flows through the pipe 58 to the outlet 59. The FdC fluid with the residues of fission products and unfissioned fissile Y elements flows to the chemical processing (CPM) (39).

[0152] Figure 7 shows a Cc circuit diagram of the collecting fluid Fd (34) to MFCC (30), followed by the outlet of the fluid contaminated with FdC (35) to the chemical processing module CPM (39). In the CPM, a reservoir (FPR) (40) stores the contaminants PF (38) for a period sufficient to reduce the activity of radionuclides with short half-lives. From 40, the FdC is transported to the RSS units MB, MR and MM, which decontaminate the fission products. RSS is described in another patent application (PCT / BR2023 / 050225, Received: July 1, 2023, Receiving Office: National Institute of Industrial Property (Brazil)). The decontaminated fluid FdD returns (37) to CPM (39). The CPM adds fresh fluid (36) and returns the Fd to the MFCC.

[0153] Figure 7 illustrates the recirculation of the refrigerant fluid in the HC circuits (31, 32, 33) between the heat generating sources in MFCC and their respective heat exchangers HE. The working fluid FdT transfers all the heat Qt to a mechanical turbine, generating mechanical work and electrical energy. Alternatively, the heat Qt is used directly for industrial or residential heating purposes.

[0154] Figure 8 shows an embodiment of MFCC1. It depicts the heat exchanger housing (67) where the working fluid FdT moves through the heat exchanger HE (61, 62, 63). The position of the ion accelerators (9) that accelerate and direct ions (19) towards the target (20) is visible. The components MK (5), RF (10), PMB (24), MR (14), the outlets (59) and the inlet (46) for the fresh Fd outlet and (59) for the contaminated FdC fluids, as well as motors (65, 66) at the bottom connected to the central shaft (21), can also be identified.

[0155] Figure 9 illustrates the HC cooling fluid circulation systems of the MFCC1. There are three cooling systems: one HCa for the accelerator target, another HCcf for the CF chamber, and the third HCcc for the CC chamber. Heat exchangers 61, 62, and 63 are used for these respective cooling systems to remove heat and transfer it to the working fluid FdT. Petition 870260065452, dated 03 / 07 / 2026, page 32 / 54 / 46

[0156] Figure 9 shows the circulation rings in the peripheral (47, 49) and internal (54, 51) parts at the top. In addition, the peripheral (48 and 50) and internal (52, 53) rings at the base are also found. The interconnection between the upper peripheral and internal rings of the collector fluid circuit Cc is indicated by 57 tubes. The CC (11) and CF (16) chambers, as well as the static moderators MK (5) and PM (15), are visible.

[0157] In summary, there are HC circulation systems for refrigerants and the Cc circuit for Fd and FdC fluids. Furthermore, the FdC fluid is cooled outside the MFCC in the chemical processing module (CPM) and in the radioactive waste treatment system (RSS) (patent submitted PCT / BR2023 / 050225, Date Received: July 1, 2023, Receiving Office: National Institute of Industrial Property (Brazil)). The chemical processing system and the fission product decontamination system are not covered by the scope of this patent application.

[0158] Figure 10 details separately the HC and Cc cooling fluid circuits. In (A), the Cc collection circuit for MFCC1 is identified with the upper rings 51 (inner) and 47 (peripheral); 52 lower rings (inner) and 48 (peripheral); interconnection 57 between the upper and inner peripheral rings; and the inlet (46) and outlet (47) of the Fd and FdC fluids, respectively.

[0159] Figure 10 (B) details the HCa cooling circuit for the accelerator target showing tubes 43 and 44, heat exchanger 60, cooling cylinder halo box 55 and moderator PM (15). HCa is shown in arrangements MFCC1,2 and 3.

[0160] Figure 10(C) illustrates the HC and Cc circuits for independent units in MFCC2 and MFCC3. In these arrangements, there are double sets of peripheral and internal rings. In MFCC3, only one set of rings (51, 53, 52, 53) is present.

[0161] Figure 10(D) shows the two independent cooling circuits HCcc and HCcf for the CC (11) (peripheral) and CF (16) (internal) chambers. Tubes 41 and 42 connected to the CF (16) heat exchanger 61 can be seen; the upper peripheral rings 49 and 50 of the CC (11); the upper internal rings 54 and base 53 of the CF (16); and the heat exchanger 62 for CC (11).

[0162] The instrumentation addresses vertical rods inside the RF reflector (10), facing the outer surface of the CC (11), and inside the MK moderator (5), facing the surface of the CF (16, 17). Petition 870260065452, dated 03 / 07 / 2026, pages 33 / 54 / 46

[0163] Among the instruments are: gamma radiation meter, neutron meter, temperature meter, pressure meter and pH meter for Fc and FcC fluids. Measurements are performed in the CC (11) and CF (16) chamber compartments. The numbers did not show such point meters.

[0164] Figure 11 illustrates the support structure (68, 69, 70), made of metal, steel or aluminum. The structure consists of fixings for positioning the rotary motors on the base (65, 66), whose shafts are fixed by magnetic bearings in the lower position. The rotor shaft is in the center of the metal fins (72). At the top of the fins, there is a circular metal base and, on it, the rotary modulator type MR (14), MB (13) or PMB (24) is fixed. In the structure, both at the top and bottom, there are metal supports where the set of magnetic rings is held. The coupling of the base with the MR modulator (14) will be magnetic without physical contact due to the high rotation speeds (~ > 105rpm); however, the fins can make contact in MB and PMB under conditions of low rotation speeds (~ < 105rpm).

[0165] The operation and geometric definitions, as well as the materials used in the permanent magnet motors (65, 66), which are connected by their shafts to the MB (13), MR (14) or PMB (24) modulators, with or without gears, with or without magnetic coupling, are well-known technologies and are based on academic and technological knowledge that has already been widely disseminated and is in the public domain. Therefore, they do not require specific or descriptive details. The simple indication of the existence of these motors, shafts and their positions is sufficient for technological implementation. Variations in the electrical and mechanical characteristics of these motors, dimensions, power and shaft coupling are possible without representing the advances in the technology specified in this patent.

[0166] Since the MFCC operates with radiation capture and fission reactions, these reactions produce X-ray and gamma ray emissions that need to be shielded and removed from the environment. However, internal gamma ray shielding was not included in the MFCC. As these devices can be coupled together, it was decided to place the gamma ray shielding in a static geometry, external to the equipment, in the environment where it will be installed.

[0167] Radiation protection in outdoor environments will not be described in this document, and the design of such protection is not part of the scope of this document. Petition 870260065452, dated 03 / 07 / 2026, page 34 / 54 / 46

[0168] The collector fluid Fd and the cooling fluid can operate at high pressure to withstand high temperature. Furthermore, both fluids must be immiscible to reduce the possibility of contaminant transfer, such as water and oil. The solution of fissile elements in Y-shaped Fd can occur using chelated substances and nanoparticles to increase the collection capacity of Fd. There are no restrictions on the material used as Fd and cooling fluids, as the choice will depend on the desired temperature, pressure, and power generation for the operation of the MFCC system.

[0169] The system is initialized with an initial loading of fissile elements into the fissile chambers and later achieves stability through the conversion of fertile Th232 or U238 into fissile material. A solid matrix MY (77) can be included in the inner compartment (28) of CF (16), as MX (3) in CC (11). The matrix MY (77), in addition to the fissile nuclides in Y in the Fd collector fluid solution (6) flowing in compartment (28) of CF (16), contains fissile elements. The Y elements in the Fd collector fluid grow over time until equilibrium concentration conditions are reached. Both fissile elements maintain subcriticality in the {MK(5), CF(16)} set with kef close to 0.95, for example.

[0170] At the start of the operation, when the concentrations of fissile nuclides Y in the collecting fluid Fd (6) are low, an added mass of fissile elements Y can be diluted in the collecting fluid. Both methods, MY (77) and Y diluted in Fd (6), can be used for the initialization of the operation.

[0171] During operation, as the fertile elements are converted into MX (3), the concentrations of nuclides from the fertile element X increase until stability is reached. From then on, the system operates with constant thermal power.

[0172] A balance of nuclide concentrations in the collecting fluid Fd (6) can be obtained by solving the balance for precursor losses X(N, Z) through: i) radiative capture (N, Z) -> (N+1, Z), ii) beta decay (β-), and iii) fission losses (n,f)PF; and, the gain in concentration of nuclides generated (N+1, Z) by radiative capture (η,γ). The gain and loss balances are based on neutron fluxes in their respective spectra in the space groups, radial, as well as the fluid fluxes of the diluents of fertile and fissile nuclides, residence time in each chamber, and define the dynamic process of conversion and multiplicative fission” of MFCC. Petition 870260065452, dated 03 / 07 / 2026, pages 35 / 54 / 46

[0173] The MFCC operation will consume fertile X elements in MX (3) and reduce the concentration of fissile elements in MY (77), thus decreasing the multiplication capacity and reducing the adopted subcriticity factor (e.g., ~0.95). However, there will be compensations due to the increase in fissile Y element concentrations in CF (16) resulting from the conversion of fertile X elements into fissile elements in CC (11).

[0174] The analysis presented in this document was supported by data obtained to show the collective behavior of particles within dynamic pre-moderators and modulators. These simulations employed nuclear data (nuclear libraries: ENDFB-V / VIII.0, JEFF-3.3, EAF-2000, TENDL-2019, citation list) and MCNP6 stochastic nuclear codes (Durkee, JW et al., MCNP6 moving objects Part I: Theory; Part II, Energy Program, 2016). In the computational analysis, the subroutines developed by the authors were coupled, considering probabilities and statistical evaluations, as well as physical phenomena of nuclear scattering and absorption interactions that occur within the MFCC. Three-dimensional collisions of two bodies with different masses, initial velocities, and angular velocities were analyzed. Multigroup treatment was considered, with spatial and energetic discretization of groups.

[0175] The analysis also considered variations in thermal vibration and temperature of the medium. The physics and equations involved in the modeling are complex, but are within academic knowledge and public domain, widely disseminated in the specialized literature in the nuclear field, as shown, among other sources, in Harrisson G. et al, Nuclear Inst. In Research in Physics, Section A., Vol. 959, 2020.

[0176] The subject can be better understood through the following examples, which are not exhaustive. Examples of embodiments of the invention Example 1

[0177] Tables 3 and 4 illustrate the material and geometric characteristics of the MFCC, in a non-limiting way. Note that the geometry and angular velocity of the MR modulator can be chosen according to the type of fertile nuclide in the internal matrix in the CC chamber, with Th-232 requiring a transmutation (η,γ) in the energy of E « 22 eV, while for U238, the energy is ~ 6.5 eV.. Petition 870260065452, dated 03 / 07 / 2026, pp. 36 / 54 / 46 Example 2

[0178] This example addresses nuclide concentrations in the Th232-U238 cycle. A model of the CF (MF) was considered with the following geometric data: thicknesses of the CC and CF chambers of Lcp 1.5 cm and Lcf 1.5 cm, respectively; Lpm of 7.5 cm; Lmk of 6 cm; Lmb of 12 cm; Lpmb of 8 cm; l rm of 100 cm; two CFi chambers (i=1,2), with radius CF1 equal to (Lpm+Lmb) and CF2 equal to (Lcfi+Lmb+Lmk+Lcfi); radius of CC equal to (Rcf2+Lmk+Lpmb+Lmr); Lrf thickness of 8 cm; and MFCC height of 70 cm. The total radius of the MFCC was 161.70 cm. The area of ​​the CC was 67293 cm2; The area of ​​CF1 was 8577 cm²; and the area of ​​CF2 was 17153 cm². The volumes of PB, CF1, and CF2 were 100.93 liters, 12.85 liters, and 25.73 liters, respectively. The total volume of CFt was 38.58 liters.

[0179] The material chosen for the modulators was MB graphite (13) with a rotation speed of 1.105 rpm, while MR (14) was made of Zircaloy with a rotation speed of 9.105 rpm. For PMB (24), the material used was polytetrafluoroethylene (PTFE) PTFEGraphite, with a rotation speed of 1000 rpm. The neutron transmission coefficients in the evaluated energy groups were KMP 0.95, KMB 0.85, KMR 0.97 and KMPB 0.90, considering absorption losses in elastic scattering. A neutron emission value of η = 2.3 neutrons per fission was adopted.

[0180] The creep reduction factors based on the area ratio were Fcfi / cf2 of 0.25 and Fcf2 / cp of 0.065. The multiplication factor adopted in (MK+CF1) and (MK+CF2) was evaluated using the MCNP code, with a first mass of fissile elements of 200 g (considered as an estimate of the equilibrium concentration in the CC volume in this analysis). The kef value obtained was 0.975, maintaining a MY (77) UO2 (3%) matrix of 0.003 m in CF1 and CF2. The multiplication factor 1 / (1-Kef) was estimated to be a value of 40 in both CF1 and CF2 and was arbitrarily kept constant during the MFCC operation; however, the positive or negative variation of the fissile material during the operation was not considered. A variation in the concentration of the MY (77) matrix in CFs may be considered in future assessments to compensate for negative changes in Kef over time.

[0181] The density of Th232 in MX (3) was 11.7 g / cm3 for metallic thorium, with A = 232. The atomic density of Th232 in MX (3) was 3.03 x 1022 atoms / cm3. In this example, the initial atomic density of the fissile element U233 dissolved in the collecting fluid was 1.3 x1019 atoms / cm3. Petition 870260065452, dated 03 / 07 / 2026, pages 37 / 54 / 46

[0182] The total surge of the distributed source in (20) was 2 x 1013n / s. The neutron flux φοπ, evaluated by diffusion in PM (15) and subsequently modulated in MB (13), reached CF1 (16) with a value of 3.86 x 109n / cm2.s.

[0183] Fission reactions were evaluated for Th233, Th234, Th235, Pa233, Pa234, Pa235, U233, U234, U235, U236, U237, U238, adopting the microscopic neutron cross-section modulated by MB in the arbitrary cold neutron energy range assumed to be 0.001 eV in this example, with a standard deviation of 0.01 eV. Table 1 illustrates the nuclide diagram in the Th232-U238 cycle and its corresponding nuclear data.

[0184] The integral of the IRR of the reaction rate in the energy spectrum domain of the neutron distribution Dn(Em, σ) and the microscopic cross-section of radiative capture (η,γ) (Si, i equal to γ) in the resonance region with energy Eo is obtained by the following expression:

[0185] [Equation 1] IRR = 2& -~2σ dE Si (E) PDF (Dn(Em,,o),E~).

[0186] On the other hand, the integral of the IRC reaction rate in the spectral domain of the neutron distribution Dn(Em, σ) multiplied by the microscopic cross-section of radiative capture (n,γ) in the low-energy region with a 1 / v behavior is given by:

[0187] [Equation 2] IRC = So 2& -~2σ dE PDF (Dn(Em,σ) ,E ) . Jl / E

[0188] where the microscopic cross-section in the thermal neutron region (ί=γ) was represented by:

[0189] [Equation 3] Si = SoJl / E

[0190] In the cold spectrum region, Eq. 3 can be used to evaluate the fission cross-section (Sf), where So is the cross-section in the cold neutron range in XS(n,f). Petition 870260065452, dated 03 / 07 / 2026, pages 38 / 54 / 46

[0191] The microscopic resonant cross-sections for radiative capture (ί=γ) and fission (i=f) in the resonance energy domain can be represented by Wigner's equation, as follows:

[0192] [Equation 4] Si = So^-4ÊJÊ(1 + (2 (E - E0) / GT)2 GT

[0193] In this case, So is the cross-section at the resonance energy Eo, given by:

[0194] [Equation 5] So = g^- (2.608 * 106 / Eo) ((A + 1) / A)2 gt

[0195] The parameters Gf, Gg, GT, and Eo are resonance parameters found in the nuclear data literature (Mughabghab, SF, Atlas of Neutron Resonances, Resonances Parameters and Thermal Cross Sections Z=1-100, 5th Edition, National Nuclear Data Center, Brookhaven National Laboratory, USA, Elsevier, ISBN: 978-0444052035-7). In a scenario where the neutron distribution follows an equivalent Normal Distribution, the integral evaluation can be done considering the Probability Density Function (PDF) of the normal distribution function. Note that the PDF normalizes the distribution D(Em, σ), obtaining an equivalent normal distribution.

[0196] In this example, the value of the integral for cold neutrons of the fission cross-section IRCffoi was evaluated at Em in the cold neutron domain (0.001 eV) and σ = 0.01 eV for each of the fissile nuclides, resulting in a value of 16.85 So for fission. Additionally, the IRCγ values ​​for radiative capture in cold neutrons were also evaluated for all fissile nuclides. The value of Em ± σ spans the cold neutron domain and can reach values ​​from 1 to 25 meV, depending on the MB design and temperature. Therefore, different values ​​can be found in this example.

[0197] The neutron flux in CF1, which reaches CF1, was evaluated by

[0198] [Equation 6]φ(.'Γ1 = ^MB . ^F1SDD2n^CF1 Petition 870260065452, dated 03 / 07 / 2026, pages 39 / 54 / 46

[0199] where Sdt or Sdd is the neutron surge from the source in n / s, where D+ ions were accelerated and collided with a tritium (T) or deuterium (D) target. The neutron flux hitting CF2 was evaluated by

[0200] [Equation 7]φί,7;2 =η^MB . K-F2·FCfE(ΦσΡ1· ^Q CF1)

[0201] where φ^1 and φ^2 are the fluxes in the fission chambers CF1 and CF2, respectively. The factors Kfi,2 are the multiplication coefficients of the pair {MK(5), CF(16, 17). On the other hand, the neutron flux that reaches CC must be:

[0202] [Equation 8]φ££ =ηfpmb kmr Kp2 fcpΣ(^F2. / #cyCf2)

[0203] The resonance integral of radiative capture for Th232 at 23.4 eV or 21.8 eV was evaluated as Sy.IRR. The neutron fluxes in CF2 and CC were evaluated at 5.11 x 1010e and 4.52 χ 109n / cm2s, respectively.

[0204] A simplified system of 13 equations, relating to radiative capture rates and fission reactions, radioactive decays, and including all fertile and fissile nuclides in the Th232-U238 cycle, was evaluated as a function of time. Initial values ​​for the atomic density of Th232 and U233 were entered at time zero.

[0205] Table 1 illustrates the set of nuclides Th232, Th233, Th234, Th235, Pa233, Pa234, Pa235, U233, U234, U235, U236, U237, and U238, whose concentrations vary in the system of equations. The elimination reaction rates by radiative capture (η,γ), β decay, and fission, as well as the production rates by (η,γ) conversion of the precursor nuclide, were evaluated. The interaction probabilities at 1 / v in the cold neutron range, as well as at resonance energies Eo, are presented for both (n^) and (n,f) reactions.

[0206] Figure 12 illustrates the atomic densities in atoms / cm3.s of the respective nuclides as a function of time for the given geometric and material conditions. The concentrations of Th232 in the MX matrix (3) remain constant, while the concentrations of the Th232 precursor nuclides increase over time, reaching equilibrium from 109 seconds and stabilizing around 1012 seconds. The density of U233, initially at 200 g in CFs, decreases from 1010 Petition 870260065452, dated 03 / 07 / 2026, page 40 / 54 / 46 seconds of operation, but is compensated by the increase in the concentration of U233 generated in the operational process of MFCC1, thus remaining continuous. Example 3

[0207] This example addresses the Th232-U238 cycle of heat and energy generation. A neutron emergence of 2x1013n / s was considered, produced by bombarding TiD targets with 120 keV deuterium ions at a rate of 2x1017d / s. The energy of the generated neutrons was 2.4. The energy consumed for this acceleration current was 3.84 kWh. This energy is accumulated in the target (20) in the form of heat and removed to the heat exchanger. A heat transfer efficiency of 95% was considered, using a coolant, multiplied by 60% heat recovery efficiency for FdT. Consequently, the recovered Qacel was 1.83 kWh, considering QDD of 10.4 W, and QDT of 56.4 W, deposited by fusion reactions if the target contains D or T.

[0208] Table 5 presents thermal parameters and efficiency evaluations of the nuclear MFCC system operating in the Th232-U238 cycle in a simplified analysis and with specific conditions of initial concentration and FT emission. The thermal energy generated in chambers CF(16) and CC(11), as well as the total thermal energy combined with Qacel, is 54.17 kWh at 105s and 30.28 kWh at 1014s, shown at two arbitrary times. The Brayton cycle was considered in the production of electricity from the transported heat, adopting an efficiency of 60% in this thermodynamic cycle. Heat is transferred from the secondary fluid FdT to the turbine, which rotates the electric generator GE. It is worth noting that the current operation presented in the MFCC1 model estimates a generation of 32 kWeh (kilowatt-electric-hour) in the first phase (non-equilibrium concentration) and 18.17 kWeh (equilibrium concentration).

[0209] Figure 13 illustrates the thermal energy generated during the operating time of the MFCC equipment functioning in the Th232-U238 cycle. In the period from 1 to 108 seconds, the MFCC operates based on the initial mass of fissile nuclides, and the equilibrium of the concentrations of precursor nuclides of the fertile element, in this case, in the Th232U238 cycle, is reached. The estimated time to reach concentration stability is one year. During this period, the MFCC operates powered by the fission of the nuclides inserted during initialization.

[0210] In the period from 108 to 1010 seconds, there is a transition in which the fissile nuclides produced by conversion in the CC begin to contribute to heat generation, Petition 870260065452, dated 03 / 07 / 2026, page 41 / 54 / 46 while the concentration of initial fissile elements decreases. This second phase of operation is relevant, since it works by producing heat based on its own fission fuel. Example 4

[0211] This example addresses the concentration of nuclides in the U238-Am243 cycle. It applies the same source parameters as in Example 3. In the U238-Am243 cycle, the MX matrix (3) consists of U238, containing 200 g of Pu239 diluted in the circulating collector fluid (6).

[0212] Table 2 illustrates the set of nuclides U238, U239, U240, U241, Np239, Np240, Np241, Pu239, Pu240, Pu241, Pu242, Pu243 and Am243, whose concentrations are the variables in the system of equations. The elimination reaction rates by radiative capture (η,γ), β decay and fission, as well as the production rates by (n^) conversion of the precursor nuclide, were evaluated. Additionally, the interaction probabilities in the 1 / ve cold neutron range (~1meV), as well as at the resonance energies Eo, for both (n,γ) and (n,f) reactions, were obtained from data available in the literature (Mughabghab SF Atlas of Neutron Resonances; Nuclear Data: EAF-2000, TENDL-2019, ENDF-B / VIII, JEFF-3.3).

[0213] Figure 12(b) illustrates the concentrations over the operating time of the nuclides involved in the U238-Am243 cycle. Equilibrium concentrations are reached from 106 seconds to 109 seconds. Concentration stability is achieved from 109 seconds onwards, making the system stable. In this case, the equilibrium concentration of Pu239 was higher than the initial concentration of Pu239 introduced into the system.

[0214] This example addresses fission in fissile materials with MB modulators (13) in the cold neutron range, in non-limiting matter. In fact, several of these fissile nuclides have suitable resonances in the 0.04 to 1 eV range. This range can be a good target for the MR modulator running on a group of these resonances. Example 5

[0215] The U238-Am243 heat and power generation cycle was analyzed. Table 6 presents the main results of the heat and power evaluation in the U238-Am243 cycle. The thermal energy produced up to 107 seconds (1 day - 1 month) was 67.94 kWth, while Petition 870260065452, dated 03 / 07 / 2026, page 42 / 54 / 46, the balance of thermal energy generation is achieved after 1 year of operation, reaching a value of 526 kWth, with a production of 316 kWeh.

[0216] Figure 13(b) illustrates the thermal energy in kWh of the MFCC system operating in the U238-Am243 cycle. This equilibrium condition remains continuous as long as the concentrations in MX, Kef and source emission remain constant. Example 6

[0217] This example shows the physical behavior of the neutron spectrum generated in the MB modulator (13), aiding the design of MB (13). The analysis considers different temperature conditions and the influence of the free molecule thermal vibration model. The number of particles evaluated was 3000, generating 850 interactions per particle. The spatial discretization was 100 groups in the radial direction. Each group represents the interval 0.005R (m). The modulator rotated at 103, 104 and 105 rpm. The material used was PTFE-Graphite, with 85% PTFE and 15% graphite powder, density of 2.15 g.cm-3. All types of collisions in the modulator were considered, scattering and absorptions. The neutron distribution Dn(Em, σ) was evaluated at each spatial and energetic position. 2D and 3D collisions were evaluated. The 2D analysis was represented in graphical form.

[0218] Figure 14 (A) shows the average energy Em of the neutron distribution Dn(Em, σ) taken from each discrete radial compartment in the MB moderator (13); consider without thermal model, at room temperature. Indices 1, 2 and 3 have different rotations.

[0219] Figure 14 (B) shows the average energy Em of the neutron distribution Dn(Em, σ) taken in each discrete radial compartment up to 100 positions in a 25 cm radius of the MB moderator (13). The Figure shows 1, 3 and 4 cases, where 1 and 3 consider non-thermal vibration, at room temperature. (1,2,3); and with a free molecular thermal model in 4, with 103 rpm, at 223 K. A suitable design for MB modulator (13) was achieved with Np ~ 35, meaning R = 10 cm, reaching a minimum of 2.5±4 meV at 220 K, 800 rpm. A realistic thermal model for the density of cold rotating polymers should be between 1 and 4 data, fitted to this spectrum result. Therefore, it is possible that a realistic modulator with temperature adjustment Tm, wn, and RMB could reproduce Em close to 1 meV. Petition 870260065452, dated 03 / 07 / 2026, pages 43 / 54 / 46

[0220] The phenomenon of thermal vibration becomes competitive in interfering with the reduction of neutron speed in combining its energy with the rotational energy of the medium. The thermal energy Et becomes a limit on the average neutron energy of the neutron distribution, however Em reaches values ​​lower than Et, since there is negative feedback due to the system dynamics forcing Em to be reduced. Example 7

[0221] In this example, we will explore the behavior of the neutron spectrum generated in the MR moderator (14) to better present the MR design.

[0222] Figure 15 shows the MR project data. The neutron transport analysis resolved 2D collisions and absorptions, having 3000 particles and 900 collisions per particle, angular velocity from 105 to 106 rpm, and taking MR at the origin, discretizing 320 radial groups. It can be observed that zirconium alloys and graphite provide similar Dn(Em,o) for high values ​​of Em, when Em is expressed as a function of radius R and angular velocity wn. This occurs since Em ~ (wn. R)2e has no dependence on the moderator material at high values ​​of wn and R.

[0223] Zirconium Zr₂O₂ material, with 51% Zr90, 11.22% Zr91, 17.15% Zr92, 17.38% Zr94, was analyzed to be MR to match the ~22 eV resonances of Th232. The MR position was evaluated in the MFCC1 model and the angular velocity adjusted. The best position was achieved in 246 groups, reaching 22 ± 7 eV. Translating these data to the actual MR radius position in MFCC1, an Lr of 60 cm and a wn of 5,105 rpm can be obtained.

[0224] In group 106, 6.5 ± 5 eV can be found in such dynamic material with Lmr and wn evaluated on the curve. For the repositioning of MR in MFCC1, there is an equivalence of (wn. LMR)2 at the origin to (wn.(RMR + LMR)2 at the actual RMR position. This means that Lr of 26.5 cm, and wn of 3.105rpm, meet Eo~Em in MFCC1. Example 8

[0225] This example deals with the criticality of the MKi-Cfi system. Let's consider an MFCC1 project having: an internal FT(20) source, with Lft of 1 cm x 6 cm placed in the center of the equipment. The length measurements are Lpm 7.5 cm PM (15); Lmbi 13.5 cm, Lcfi 1.5 cm, Lmki 8 cm, Lmb2 14 cm, Lcf2 1.5 cm, LMk2 7 cm; Lpmb 8 cm Lmr 40 cm, Lcc 1.5 cm, Lrf 8 cm, support Ls 0.5 cm; Hmfcc 80 cm, Hcc and Hcf 56 cm. These were Petition 870260065452, dated 03 / 07 / 2026, p. 44 / 54 / 46 considering the following materials: MR (14) of graphite (2.25 g / cm3), MB (13) of graphite, PMB (24) of graphite (2.25 g / cm3), MK1 and MK2 (5) of light water, RF of PTFE (2.16 g / cm3), FT (20) source of deuterium gas, steel support (7.852 g / cm3), MX (3) Lmx 8 mm of Th232 in ThC (10.6 g / cm3), MY Lmy 10 mm of UO2 (10.97 g / cm3), 5% enrichment in the initial condition.

[0226] Recalling that the MY (77) matrix is ​​introduced into MFCC1 to improve criticality in the initial operating period before the concentrations of fissile materials reach equilibrium. Simulations of the multiplicative factor MK (5) were evaluated in the MCNP6 code, showing the effectiveness of introducing the MK (5) matrix close to the MY matrix to amplify neutrons produced by fission in the CF1 and CF2 chambers. MFCC1 was modeled in MCNP6 geometry. Natural and heavy water were used as material for MK (5); while UO2-enriched uranium was used in MY (77). The results show that the criticality in the MK fissile system is 0.94495 for the starting condition. This condition was used to achieve equilibrium concentrations in the Th232-U238 and U238-Pu243 cycles in previous examples 2 and 4. Example 9

[0227] The chemical processing module helps to separate the fission products from the fissile nuclides that did not undergo fission, collected by the collecting fluid FdC. The fissile products are directed to a reservoir for further treatment. The residence time in this reservoir helps to reduce the activity of nuclides with short half-lives.

[0228] The decontaminated collection fluid FdD undergoes concentration adjustments with the solvent. Chelating agents are introduced to assist in collecting the fissile products converted into MX (3) and to transport them to CFs (16).

[0229] A variety of chelating complexes can be employed to address the diverse ionic valences of fissile products in solution. The concentration of these reagents is controlled and adjusted by the chemical processing module.

[0230] In this decontamination line, different neutron spectra expose the contaminant solution, targeting their respective distinct nuclear resonances, which trigger the activation of neutrons from each of the respective fissile products. In each specific resonance spectrum, a long-lived radionuclide present in Petition 870260065452, dated 03 / 07 / 2026, pages 45 / 54 / 46 PF reacts (η,γ) converting into a stable nuclide or a new short-lived radionuclide.

[0231] Table 1 - Th232-U238 Cycle. 1 / v(n,g) 1meV 1100 R(n,g) 0.48eV 2500 Th232-U238 / U235 Np (st) (n,g) Np(st) 237 ^ 238 (n,f) i i 1 / v(n,f) 1meV 0.1 1meV 10000 R(n,f) 5.5 0.07 1.4 eV 900 1 / v(n,g) 1meV 200 1meV 500 1meV 900 1meV 9 1meV 1 R(n,g) .5eV 200 0.2 30000 0.25eV 50 5.5 10000 2 eV 12000 3.5eV 500 1.2eV 45 U(st) (n,g) U(st) (n,g) U(st) (n,g) U(st) (n,g) U (st) 233 ^ 234 ^ 235 ^ 236 ^ 237 i i i i i 1 / v(n,f) 1meV 3000 1meV 0.3 1meV 2.5E3 1meV 0.4 1meV 0.01 R(n,f) 1.6eV 1000 5.2eV 1 0.3eV 105 5eV 100 5 eV 500 1.0eV 110 1 / v(n,g) 1 meV 250 1meV 1 m | 6.76d \ (n,g) STOP R(n,g) 0.8 50 0.3 eV 1 m U (st) U (st) 1.35 2500 237 238 26,975d 1.7 5000 6.7h 24.43m i b- \ \ \ 1meV 0.1 m Pa (n,g) Pa (n,g) Pa 7.2 eV 1 m 233 ^ 234 ^ 235 (n,f) i i i 1 / v(n,f) 1 meV 0.5 1meV 2.5E4 1meV 1 m decay R(n,f) 1.3eV 6.0 0.3eV 1.5E4 eV 1 m m=min 1.7eV 11 XS (b) 1 / v(n,g) 1meV 40 1meV 10000 1meV 10 m->10-3 R(n,g) 21.82eV 1800 6eV 2000 30eV 5000 23.45eV 2800 6.5eV 4000 21.83m | 24.7d 7.16m b- FERTIL \ \ \ Th(st) (n,g) Th (n,g) Th (n,g) Th 232 ^ 233 ^ 234 ^ 235 (n,f) iiii 1 / v(n,f) 1meV 0.2 m 1 meV 250 1meV 0.1 1meV 10 R(n,f) > 2eV 1 m >2eV 50 28eV 30 0 eV 1 m. Petition 870260065452, dated 03 / 07 / 2026, page 46 / 54 / 46

[0232] As a result, the diagram shows that the waste consists of stable nuclides or short-lived radionuclides. Chemical separators adjust the concentrations and evaluate the output fluids for the activity of the input and output radionuclides. The chemical processing module contains gamma spectrometry, which intelligently finds the set of radionuclides present and adjusts the units to fit specific resonance energies.

[0233] The chemical processing module, collector fluid types and coolant are not within the scope of this article. [0234 ]Table 2 - U238-Am243 Cycle. 1 1 U238-Pu239 / Am243 1meV 1.4eV 400 20000 10h 7330a \ \ decay m=min Am (n,g) Am XS (b) m=0.001 243 ^ 244 1 meV 2500 1 / v(g) 140 meV 1 meV 2000 0.25eV 600 1meV 100 R(n,g) 0.3eV 2500 1 eV 100000 4eV 1000 3eV 37000 b- 14.4a 4.96h (n,g) Pu(~st) (n,g) Pu(~st) 239 ^ 240 ^ 241 ^ 242 ^ 243 (n,f) 4 4 4 4 1 / v(n,f) 1 meV 3500 1 meV 0.3 1 meV 5000 1 meV 0.3 1 meV 3500 1eV 40 0.25eV 3000 2.8eV 20 1 / v(n,g) 1 meV 200 1 meV 1000 1 meV 0 P(n,g) 0.3 eV 300 eV eV 0 b- 2.355d 1.03m N \ 3 \ m (n,g) Np (n,g) Np 239 ^ 240 ^ 241 (n,f) 4 4 4 1 / v(n,f) [T 1 meV 100 1 meV 1200 1 meV 0 R(n,f) 0.25eV 80 0.04eV 100,V / v(n,v) 1meV 15 1meV 100 1meV 1 0 R(n,g) 6.7eV 7200 0.4eV 50000 eV 18 0 b- 23.47m 14.1x 7.16m \ \ \ U(st) FERTIL U (n,g) U (n,g) U 2929 ^ 240 ^ 241 (n,f) 4 4 4 4 1 / v(n,f) 1meV 0.0001 1 meV 70 1 meV 0.001 1 meV 0 R(n,f) 7eV 0.0001 0.4eV 22000 IR 0.6 eV Petition 870260065452, of 03 / 07 / 2026, p. 47 / 54 / 46

[0235] Table 3 - Material and geometric parameters in the Th232-U238 cycle. Comp. Mat. LR[m] Wn [rpm] PM Polyethylene 0.075 0 MB (1.2) PTFE- Graphite 0.125 1.103 MK (1.2) Heavy or Light Water 0.100 0 MR Zircaloy or Graphite 0.60 6.105 PMB Graphite 0.120 1.103 CCP Zircaloy 0.015 0 CI (1.2) Zircaloy 0.015 0 FP Li7(p,n) or D(d,n), D(T,n) 0.012 0 RF PTFE- Graphite 0.080 0 MX Matrix Th232, ThC2 0.005 0 MY Matrix U233-UO2 (3%) 0.003 0

[0236] Table 4 - Material and geometric parameters in the U238-AM243 cycle. Comp. Mat. LR[m] Wn [rpm] PM Polyethylene 0.075 0 MB (1.2) PTFE- Graphite 0.120 1.103 MK (1.2) Light or heavy water 0.100 0 MR Graphite 0.260 5*105 PMB PTFE- Graphite 0.150 1.103 CC Zircaloy 0.015 0 CI1 Zircaloy 0.015 0 CI2 Zircaloy 0.015 0 FP Li7(p,n) 0.012 0 RF PTFE- Graphite 0.10 0 MX Natural U238 matrix, UC2 0.005 0 MY UO2 matrix, 3% enriched 0.003 0

[0237] Table 5 - Thermal parameters and efficiency in the Th232-U238 cycle. Thermal parameters T=105s T=1014s Q (CF1+CF2+CC) 50.47 26.58 Total Q (KWth) 54.18 30.29 Brayton cycle efficiency 60 60 Electrical energy (KWeh) 32.50 18.17 Electrical efficiency (ef*KWth-KWeh / ef*KWth) 88 78 Petition 870260065452, dated 03 / 07 / 2026, pages 48 / 54 / 46

[0238] Table 6 - Thermal parameters and efficiency in the U238-Pu243 cycle. Thermal parameters T=105s T=1014s Q (CF1+CF2+CC) 64.23 523.19 Total Q (KWth) 67.94 526.90 Brayton Cycle Efficiency (ef) 60 60 Electrical Energy (KWeh) 40.76 316.14 Electrical Efficiency (ef*KWth-KWeh / ef*KWth) 92 81 Industrial Application

[0239] The MFCC equipment and its arrangements, as described in this document, operating on the Th232-U238 or U238-Am243 cycles, can generate heat for industry, chemical processes, residential heating and electricity. List of Reference Signs 1. MC module for converting fertile material. 2. MF fission module. 3. MX matrix of fertile material in CC. 4. MS module of the source, includes primary neutron source (PF). 5. MK static moderator module for multiplicative fission 6. Transport of collector fluid from CC to CF in a dependent unit {MC, MF, MS}. 7. Compartment for fission in CF 8. Transport of collector fluid from CC to CF in independent units {MC, MS} and {MF, MS}. 9. Box for the ion accelerator. 10. Neutron RF reflector. 11. DC conversion camera. 12. Cooling chamber for cryogenic fluid in PM when MB is applied. 13. MB cold neutron energy modulator. 14. MR resonance modulator in MC. 15. PM previously static moderator of the source 16. CF1 first fission chamber in multiple conditions. 17. CF2 second fission chamber in multiple conditions. 18. MF second fission module in multiple conditions. 19. Halo tube for ion accelerator. 20. Solid target for ion accelerator and neutron generation. 21. Central radial axis of the moderator and modulator units. 22. Central gear of the first rotary motor. 23. Radial halo gear of the second rotary motor. 24. Low-energy PMB moderator in MC. 25. PMB previously used as a low-energy moderator in MF. 26. Internal compartment of the slaughterhouse in CC for transporting refrigerant fluid. 27. Internal compartment of the slaughterhouse in CF for transporting refrigerant fluid. 28. Internal liquid fission compartment in the CF. Petition 870260065452, dated 03 / 07 / 2026, pages 49 / 54 / 46 29. Internal fluid collector compartment in DC. 30. Converter Nucleus and Multiplicative Fission - MFCC 31. HCa - Transport of cooling fluid for cooling the accelerator target. 32. HCcf - Transport of refrigerant fluid for CF cooling. 33. HCcc - Transport of refrigerant fluid for DC cooling. 34. Fd - PF-free collector fluid for MFCC. 35. FdC - Contaminant collector fluid (fissile liquid) of the MFCC. 36. Fd update fluid input link. 37. FdD - decontaminated fluid from RSS units. 38. Fluid transport from PQ to RF RT. 39. Chemical Processing Module CPM 40. VSHL FPR - Very Short Half-Life Fission Product Repository 41. CF cooling inlet pipe 42. CF cooling outlet pipe 43. Accelerator chamber (AC) cooling inlet pipe. 44. Accelerator Chamber (AC) cooling outlet pipe 45. DC cooling inlet pipe. 46. ​​Inlet fluid collector tube for DC. 47. Ring tube 48. Ring tube 49. Ring tube 50. Ring tube 51. Ring tube 52. Ring tube 53. Upper ring tube of the DC inlet collector fluid. Lower fluid pressure at the DC intake caliper. Upper coolant pressure at the DC outlet. Lower coolant pressure at the DC inlet. upper fluid level of the inlet clamp in CF. lower outlet fluid collector in CF. lower inlet coolant level of the CF. 54. Upper ring tube for CF outlet coolant. 55. Cylinder housing of the halo of the "cooler" of the originating ion target. 56. Connection of the lower collector ring to the CC. 57. Upper link of the DC to CF collector fluid. 58. Lower outlet link for CF collector fluid. 59. External outlet link for the collector fluid. 60. Heat exchanger for the throttle target. 61. Refrigerant fluid heat exchanger CF. 62. DC refrigerant heat exchanger. 63. Working fluid inlet FdT. 64. Working fluid outlet FdT. 65. High-speed permanent magnet motor for MR. 66. High-speed permanent magnet motor for MB and PMB. 67. Heat exchanger fluid box. 68. Upper support for PM, MK, CC and CF, and throttle box. 69. RF side-holding support 70. Support base - fixing for high-speed motors. 71. Measuring motor speed 1 72. Measuring engine speed 2 73. MR support holding propeller. Petition 870260065452, dated 03 / 07 / 2026, pages 50 / 54 / 46 74. PM and MB propeller support holding company. 75. Magnetic top support for MR. 76. Lower magnetic support for MR. 77. MY matrix of fission material in FCs to support multiplication. List of citations

[0240] Techno-economic Comparison of Geological Disposal of Carbon Dioxide and Radioactive Waste IAEA-TECDOC-1758h IAEA-TECDOC-1758 / 978-92-0-110114-3 244 pages.

[0241] Planning and Design Considerations for Radioactive Waste Geological Waste Programs, IAEA-TECDOC-1755 / 978-92-0-109914-3 80 pages Published: 2014.

[0242] Duderstadt, James J, Hamilton, Louis J., Nuclear Reactor Analysis, John Wiley & Sons, Inc, Michigan, 1976

[0243] Mughabghab, SF, Atlas of Neutron Resonances, Resonances Parameters and Thermal Cross Sections Z=1-100, 5thEditon, National Nuclear Data Center, Brookhaven National Laboratory, USA, Elsevier, ISBN: 978-0-444052035-7.

[0244] JEFF-3.3, Joint Evaluated Fission and Fusion File (JEFF), NEA Data Bank, oecdnea.org / dbdata / jeff / jeff33 / index.html, Accessed 2023.

[0245] EAF-2000; Neutron-induced cross-section library, The European Activation, File EAF-99-JEFF-3 activation file, 2000. doi.org / 10.1080 / 00223131.2000.10875007. Published online: 27 Aug 2014.

[0246] TENDL-2019; TALYS-based evaluated nuclear data library, A.J. from: Koning, D. Rochman, J. Sublet, N. Dzysiuk, M. Fleming and S. van der Marck, TENDL: Complete Nuclear Data Library for Innovative Nuclear Science and Technology, Nuclear Data Sheets 155 (2019).

[0247] ENDF-B / VIII.0 - Evaluated Nuclear Data Library National Nuclear Data, www.nndc.bnl.gov / endf-b8.0 / index.html Accessed: may, 2003.

[0248] Durkee J.W. et al., MCNP6 moving Objects part I: Theory, Prog. Nucl. Energy, 2016. Petição 870260065452, de 03 / 07 / 2026, pág. 51 / 54 / 46

[0249] Durkee J.W. et al. MCNP6 moving objects. Part II: Simulations. Prog. Nucl. Energy, 2016.

[0250] Harrisson G., Li G., Van Der Ende B., Rogger R. B., Tun Z. Simulation of a rotating neutron moderator, Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, Vol. 959, 11 April 2020, 163562. Literatura de patentes

[0251] Wo2016 / 060867 a1, Smick, Noah, et al. Generating Neutrons Using a Rotating Neutron Source Material.

[0252] US2023 / 0024338, Mark Reed et al, Skewed-Pin (SPIN) Moderator locks for Nuclear Reactors, 2023.

[0253] Campos, Tarcisio Passos Ribeiro de; Campos, Alberto Mizrahy. submitting patent PCT / BR2023 / 050225, Date of Receipt: 01 July 2023, Receiving Office: National Institute of Industrial Property (Brazil)). Petição 870260065452, de 03 / 07 / 2026, pág. 52 / 54

Claims

1 / 2 CLAIMS 1. Equipment, Multiplicative Fission and Conversion Core - MFCC(30), characterized by optimizing the neutron reaction rate of the (η,γ) radiative capture of X nuclides, and (n,f) fission of Y nuclides, generating a neutron distribution (Dn(Em,a), Em - average energy, σ - standard deviation) in a selective domain of the neutron spectrum fitted to a respective XS cross-section type of the X and Y nuclides.

2. MFCC, according to claim 1, characterized by the arrangements MFCC1, MFCC2 and MFCC3, operating in one of the Th232-U238 and U238-Am243 cycles, where X is one of the fertile Th232 and U238 nuclides, and by an MR modulator tuning Em to Eo (Em ~ Eo) where Eo is one of the well-defined resonance energies of 21.8 eV and 23.4 eV of Th232, and 6.65 eV of U238, optimizing the conversion reaction X(n^)Y into fissile Y nuclides; and MB modulator tuning Em in the cold neutron spectra optimizing Y(n,f) when XS(n,f) maintains 1 / v behavior; and MR modulator adjusting Em ~ Eo with resonance energy Eo of nuclides Y, when XS(n,f) is resonant type.] 3. MFCC, according to claims 1 and 2, characterized by grouping the following modules: MS(4) - source module, MF(2) - fission module, MC(1) - conversion module, composing one of the following sets: serial {MC(1), MF(2), MS(4)}, i.e., arrangement MFCC1; parallel {MC(1), MS(4)} and {MF(2), MS(4)}, i.e., arrangement MFCC2; and individual {M, MS(4)} where M operates as MC(1) and MF(2), in distinct periods, said arrangement MFCC3; wherein the modules MC(1) consist of {RF(10), CC(11), MR(14), PMB(24)}, MF(2) can be repeated (MF(2,18)) and consist of one of the sets {MK(5), CF(16), MB(13)} and {MK(5), CF(16), MR(14), PMB(24)} and MS(4) consist of {PM(15), FT(20)}.

4. MFCC, according to claims 1 to 3, characterized by PM(15) representing a static pre-moderator, PMB (24) a low-energy dynamic pre-moderator, MR (14) a dynamic modulator to match a well-defined resonance energy, MB (13) a low-energy dynamic modulator in the cold neutron domain, MK(5) a static moderator, RF(10) a static neutron reflector, FT(20) a neutron source inserted in PM(15), CC(10) chamber for fertile material and CFs(16,17) fissile chamber, with CC(11) and CFs(16,17) subdivided into two compartments (26,29) and (27,28), respectively; where RF(10), PMB(24), PM(15), MR(14), MB(13), MK(5) are solid cylindrical halos arranged on the same axial axis (21). Petition 870260032548, dated 08 / 04 / 2026, page 4 / 64 2 / 2 5. MFCC, according to claims 1 to 4, characterized by having neutron distribution modulators Dn(Em^) of two types: low-energy modulator MB(13) with Em in the cold neutron domain; and, resonant modulator - MR(14) with Em approaching the resonance energy Eo; wherein the inner radii Ri and outer radii Re of the cylindrical halos MB and MR and their operating angular velocity wn maintain values ​​of Ri and Re in the range of 0.1 to 1.5 m, and wn from 102 to 106 rpm.

6. MFCC, according to claims 1 to 5, characterized in that MFCC1 and MFCC2 contain a matrix of solid material MX(3) consisting of fertile nuclides X within the inner wall of compartment (29) in CC(11), and a matrix of solid material MY(77) of fissile nuclides Y within the inner wall of compartment (28) in chambers CF (16,17); and MFCC3 containing in its single chamber C the material matrix Mi(78) filled with one of the i being X and Y; within the cylinder chambers CC(MX) and CF(MY).

7. MFCC, according to claims 1 to 6, characterized by having a circulating collector fluid circuit Fd (6), wherein Fd (34) is a solution flowing between compartment (29), through the matrix MX(3), removing fissile nuclides Y and transferring them to compartment (28) in fissile chambers CF(16, 17), in a continuous inlet (46) and outlet (59) of the flow over time; subsequently, the contaminated fluid FdC (35), which carries fission products PF, is transferred to the chemical processing module (CPM) (39) for treatment and recirculation.

8. MFCC, according to claims 1 to 7, characterized by having arrangements MFCC1 and MFCC2 containing independent cooling circuits HC (31,32,33), HCcc (45,46,62) to remove heat Qc from chamber CC(11) in compartment (26), HCcf (41,42,61) to remove heat Qf(61) from one or more chambers CF (16,17) in compartments (27), and HCa (43,44,62) to remove heat Qa(60) from the target (20) of the neutron source in compartment (55); wherein the heat is removed by heat exchangers (60,61,62) to the working fluid FdT (63, 64); while MFCC3 retains HCa and an HC circuit. Petition 870260032548, dated 08 / 04 / 2026, p. 5 / 64

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