108 results about "Nuclear fission" patented technology

The invention relates to a new technology for depositing a CrAlSiN gradient coating with high-temperature oxidation corrosion resistance and excellent mechanical properties on a supercritical water-cooled reactor fuel clad surface in a nuclear fission reactor. The CrAlSiN gradient coating is deposited on the surface of a base material by adopting a multi-target reaction magnetron sputtering method, and the technology comprises the following four continuous stages of: 1, preparing a Cr gradient coating; 2, preparing a CrAl gradient coating; 3, preparing a CrAlN gradient coating; and preparing the CrAlSiN gradient coating, and annealing. By reasonably designing the gradient variable microstructure of each element, the anti-oxidation temperature of the coating reaches 950 DEG C, the hardnessof the coating reaches over 37GPa, and the adhesive force of the coating adhered to the base material reaches 34N; the coating also has excellent thermal shock resistance, abrasion resistance and thelike; and the service property of the supercritical water-cooled reactor fuel clad part can be greatly improved, and the service life of the clad part can be greatly prolonged.

In order to solve the high-speed cancer excited state problem, a biological retarder is needed. Cancer energy is converted into intramolecular transfer or other vibrational state transfer through collision. By means of the nucleus retarder principle, a neutron and a retarder atomic nucleus are subjected to collision so that the speed can be decreased, and the retarder which does not absorb neutrons and does not react with neutrons is selected. An important task of the cancer biology and even the natural science is that which material can bear a cancer nuclear fission biological retarder. According to repeated experiments, various safety factors are synthesized, and finally a biological moderator is correctly selected through a successful experiment. Bifidobacterium is free of toxicity and harm to a body, and the biological retarder can be ideal for treating a cancer. In the future, more microorganism retarders will be produced, the biological retarder is used for decelerating tumors, a proper amount of deceleration molecular nuclear energy can be used as senile cell addition nuclear energy, and the biological retarder gives power to biological science and will play an indispensable critical role.

A molten salt reactor is described that includes a containment vessel, a reactor core housed within the containment vessel, a neutron reflector spaced from the containment vessel and positioned between the core and the containment vessel, a liquid fuel comprised of a nuclear fission material dissolved in a molten salt enclosed within the core, a plurality of heat transfer pipes, each pipe having a first and a second end, wherein the first end is positioned within the reactor core for absorbing heat from the fuel, a heat exchanger external to the containment vessel for receiving the second end of each heat transfer pipe for transferring heat from the core to the heat exchanger, and at least one and preferably two or more reactor shut down systems, where at least one may be a passive system and at least one or both may be an active or a manually operated system. The liquid fuel in the core is kept within the core and heat pipes are used to carry only the heat from the liquid core to the heat exchanger.

Disclosed is a coolant with dispersed neutron poison micro-particles, used in a supercritical water-cooled reactor (SCWR) emergency core cooling system. Since the neutron poison micro-particles are uniformly dispersed in the coolant of the emergency core cooling system for a long period time, their fluidity is not lowered even though the polarity of water is changed in a supercritical state. Therefore, the neutron poison micro-particles absorb neutrons produced from nuclear fission in a nuclear reactor core. Accordingly, the neutron poison micro-particles can be appropriately used as a means for controlling neutrons and stopping a nuclear reactor in the SCWR emergency core cooling system.

The preparation method of radiation-sensitive copolymer carrier for coating radiated nanoparticles and / or chemotherapy drugs includes forming a nanosphere by diselenide block copolymers and DSPE-PEG-biomarkers to coat chemotherapy drugs and / or radiated nanoparticles that can be released from the opened nanosphere by protons penetrating tissue during proton therapy. The treatment effect of proton therapy is enhanced by two ways of using the radiated nanoparticles released from an opened nanosphere to produce nuclear fission with the protons for releasing electrons to destroy cancer cells of tumor and the chemotherapy drugs released from the opened nanosphere for distributing among tissue to kill the cancer cells of the tumor.

The preparation method of radiation-sensitive copolymer carrier for coating radiated nanoparticles and / or chemotherapy drugs includes forming a nanosphere by diselenide block copolymers and DSPE-PEG-biomarkers to coat chemotherapy drugs and / or radiated nanoparticles that can be released from the opened nanosphere by protons penetrating tissue during proton therapy. The treatment effect of proton therapy is enhanced by two ways of using the radiated nanoparticles released from an opened nanosphere to produce nuclear fission with the protons for releasing electrons to destroy cancer cells of tumor and the chemotherapy drugs released from the opened nanosphere for distributing among tissue to kill the cancer cells of the tumor.

The invention discloses an underground nuclear plant with nuclear island cavern groups distributed in an L shape. The underground nuclear plant comprises nuclear islands used for generating steam through nuclear fission energy and arranged in underground cavern groups, a reactor factory building cavern used for containing reactor factory buildings is arranged in the middle in the underground cavern groups, and auxiliary cavern groups used for containing auxiliary factory buildings are arranged around the reactor factory building cavern in an L shape. By means of the underground nuclear plant with the nuclear island cavern groups distributed in the L shape, an existing underground cavern digging technology meets the building requirement of the underground nuclear plant, the number of caverns contained in the auxiliary cavern groups is small, and stability of surrounding rock is facilitated.

The invention relates to a preparation method of an aerogel material capable of efficiently absorbing iodide ions and iodide steam, and relates to the preparation method of the aerogel materials. The preparation method of the aerogel material aims to solve the problem that at present, radioactive 129 I and 131 I generated in nuclear fission reaction are hard to catch and control, and easy to diffuse. The prepared material reacts with iodide ions and iodide steam, thereby mainly forming AgI and solidifying I2 monomers. The preparation method of the aerogel material comprises the following steps of 1. preparing natural macromolecular nano-fibril aqueous dispersion; 2. freezing and drying the natural macromolecular nano-fibril aqueous dispersion to form ultralight natural macromolecular nano-fibril porous materials, soaking the porous materials in a silver-ammonia solution, dispersing the porous materials by ultrasonic waves to be loaded with complex containing Ag+, and then freezing and drying the resultant again; 3. then soaking the resultant with thin alkali liquor again, and enabling the complex to react to form silver oxide to obtain nano-fibril loaded with the silver oxide; 4. and cleaning and drying the fibril to obtain the aerogel materials capable of efficiently absorbing iodide ions and iodide steam after being separated. The preparation method is applied in the aspects of nuclear industry, sewage treatment, electronic elements and the like.

The invention describes a product and a method for generating electrical power directly from nuclear power. More particularly, the invention describes the use of a liquid semiconductor as a means for efficiently converting nuclear energy, either nuclear fission and / or radiation energy, directly into electrical energy. Direct conversion of nuclear energy to electrical energy is achieved by placing nuclear material in close proximity to a liquid semiconductor. Nuclear energy emitted from the nuclear material, in the form of fission fragments or radiation, enters the liquid semiconductor and creates electron-hole pairs. By using an appropriate electrical circuit an electrical load is applied and electrical energy generated as a result of the creation of the electron-hole pairs.

An anti-oxidation iron-based superalloy and a preparation method thereof, which belong to superalloys and a preparation method thereof, solve the problem of unsatisfactory oxidation resistance of existing iron-based superalloys under high-temperature conditions, so as to improve serviceability and broaden high-temperature application fields. The anti-oxidation iron-based superalloy of the present invention has the composition mass percentages of: 12%≤Cr≤14%, 2%≤W≤3%, 0.3%≤Ti≤0.4%, 0.2%≤Si≤2%, 0.25%≤ Y2O3≤0.3%, the balance is Fe; it is made by mechanical alloying, molding and vacuum sintering, and the matrix of the final sintered body is α-(Fe, Cr) single-phase solid solution with uniformly distributed oxides in the matrix. The invention has high production efficiency and low cost, and the prepared anti-oxidation iron-based superalloy has reduced oxidation weight gain and improved anti-oxidation ability under the atmospheric condition of 850°C; the tensile strength at room temperature is ≥600MPa, and the elongation rate is ≥25%, which meets the requirements of automobiles. Requirements for the use of high-temperature structural parts such as engines and gas turbines, nuclear fission fuel cladding tubes, and first wall structural materials of nuclear fusion reactors.

A method and a system for fissile content measurement that utilizes a detector configured to detect fast neutrons. An external radiation source may be used to induce fission in a sample to allow the measurement of a fissile material of the sample with a low spontaneous fission probability. Analyzing the sample may be based on the energy spectrum of emitted neutrons. That is, the energy information regarding the energy of the fast neutrons is obtained, and the fast neutrons as having a high likelihood of originating in a nuclear fission process as opposed to originating in an (alpha,n) reaction by utilizing the obtained energy information are classified to analyze the sample. Alternatively, a position of interaction in the detector of neutron emitted by the sample is measured, and this position is retraced back through intervening material(s) between the detector and the sample to determine the spacial geometry of the sample.

The invention is a preparation technology of Brachionus plicatilis microkernel. The water pollution (such as heavy metal cadmium) is dangerous to the Brachionus plicatilis. In cell, the cell nuclear fission of Brachionus plicatilis is influenced and the microkernel can be produced. The microkernel number can appraise the toxicity degree of pollution. The preparation method includes the rotifer toxicity, tabletting, coloration and observation. The figure in abstract shows the size and form of the Brachionus plicatilis microkernel.

The invention belongs to the physical technical field of reactors of nuclear power plants, and in particular relates to a reactor power coefficient measuring method. After nuclear fission, the reactorreach stable criticality, the reactor core power is P1, the reactor core reactivity is rho1, and positive reaction is introduced to the reactor, so that the reactor power is increased continuously, the positions of starting and finishing control rods are kept unchanged during the period; negative reactive feedback is brought to the reactor core as the power increases due to a heating effect of afuel; the final reactor core reactivity is gradually reduced to 0; and the reactor core power is P2, the reactor core reactivity is rho2, and the specific value of change rho1-rho2 and powder change P1-P2 of the reactor core reactivity is calculated to obtain the power coefficient. Test measurement under a zero power platform after different reactors are critical can be conducted, and the reactorpower coefficient is obtained accurately.

A unique space propulsion engine is disclosed, which directly uses the kinetic energies of nuclear fission fragments to generate thrust. At the moment of fission, approximately 85% of the total energy produced is kinetic, contained within fission fragments traveling at 4% the speed of light. The propulsion of rockets and other space devices is conventionally accomplished by hurling mass overboard at high velocities, in accordance with the principles of Newton's third law of motion. An important parameter for quantifying propulsion performance is specific impulse (Isp). Propulsion technologies that support today's rocket missions are primarily based on chemical reactions to produce thrust, and are characterized by Isp values peaking at about 400 seconds. Space concepts using nuclear energy solid-core reactors to heat and exhaust a stored material might operate up to 800 seconds, while more advanced nuclear gas-core reactors and nuclear explosive propulsion have a theoretical limit in the 3000-6000 seconds range. The theoretical Isp of fission fragment kinetic energy propulsion is 1,220,000 seconds, a quantum leap above current technologies and other advanced concepts, up to the level essential for missions to the outer reaches of our solar system and beyond.

The invention discloses a large nuclear power station with underground reactor and radioactive auxiliary plant. The large nuclear power station comprises a nuclear island and a conventional island, wherein the nuclear island generates steam by nuclear fission, the conventional island uses the steam generated by the nuclear island to generate electricity, the large nuclear power station is characterized in that the nuclear island is arranged in a underground cavern group excavated in hard rocks by men, the conventional island is on the ground, a passive pool is arranged at the upper part of the cavern group, and a nuclide migration protective system is also arranged outside the cavern group. The large nuclear power station is consistent with the passive concept of the third generation of nuclear power technology, effectively prevents nuclear radiation diffusion in accidents, has the good resistance to shock, prevents tsunami and typhoon from damaging nuclear buildings, has the good safety, and can resist the terrorist attack.

The invention describes a product and a method for generating electrical power directly from nuclear power. More particularly, the invention describes the use of a liquid semiconductor as a means for efficiently converting nuclear energy, either nuclear fission and / or radiation energy, directly into electrical energy. Direct conversion of nuclear energy to electrical energy is achieved by placing nuclear material in close proximity to a liquid semiconductor. Nuclear energy emitted from the nuclear material, in the form of fission fragments or radiation, enters the liquid semiconductor and creates electron-hole pairs. By using an appropriate electrical circuit an electrical load is applied and electrical energy generated as a result of the creation of the electron-hole pairs.

Beta and alpha-ray particles emitted by radio-isotopic by-products of nuclear fission, such as nickel 63, are used as a power source at the cathode of a microwave generating magnetron. Such particles include high speed, high energy electrons having a large EMF associated therewith. In the magnetron, a radial electrical vector, between the cathode and anode, interacts with an axial magnetic vector to produce a cloud of electrons that rotates about the magnetron axis. The speed, geometry and density of the rotating cloud may be modulated by an external RF input or grids within the interaction space of the magnetron. At the periphery of the interaction space is a polar array of anode cavities into which the rotating field induces an LC equivalent parameter that includes high energy microwaves that may be used as an input for the generation of AC or DC power.

A heat exchanger, methods therefor and a nuclear fission reactor system. The heat exchanger comprises a heat exchanger body defining an exit plenum chamber therein shaped for uniform flow of a hot primary heat transfer fluid through the chamber. A plurality of adjacent heat transfer members are connected to the heat exchanger body and spaced apart by a predetermined distance for defining a plurality of flow passages between the heat transfer members. The flow passages open into the exit plenum chamber. Spacing of the heat transfer members by the predetermined distance evenly distributes flow of the primary heat transfer fluid through the flow passages, across the surfaces of the heat transfer members and into the exit plenum chamber. Each heat transfer member defines a flow channel therethrough for flow of a cooler secondary heat transfer fluid.

The invention discloses a nuclear island cavern group annular arrangement underground nuclear power plant comprising a nuclear island producing steam with nuclear fission energy. The island is arranged in an underground cavern group. The underground cavern group comprises a reactor factory building cavern used for accommodating a reactor factory building and an auxiliary factory building cavern group, all of which are arranged underground. The auxiliary factory building cavern group is annularly arranged around the reactor factory building cavern. With the underground nuclear power plant nuclear island cavern annular arrangement form, existing underground cavern evacuation technologies can satisfy the construction requirements of the underground nuclear power plant. Being annularly arranged, the cavern group has an arrangement position substantially same with that of nuclear island factory buildings of a ground nuclear power plant. Therefore, less adjustment is required on an existing ground nuclear power plant technology system.

A fuel rod for a nuclear fission reactor is disclosed and claimed. The fuel rod includes an elongate hollow cladding configured to retain a nuclear fuel therein. The cladding includes an elongate hollow tube. Fiber layers are positioned around the outside surface of the tube or within the tube forming an integral part thereof. Both the tube and the fibers are formed of a ceramic material. A fuel assembly including a plurality of such fuel rods is also disclosed and claimed.

A traveling wave nuclear fission reactor, fuel assembly, and a method of controlling burnup therein. In a traveling wave nuclear fission reactor, a nuclear fission reactor fuel assembly comprises a plurality of nuclear fission fuel rods that are exposed to a deflagration wave burnfront that, in turn, travels through the fuel rods. The excess reactivity is controlled by a plurality of movable neutron absorber structures that are selectively inserted into and withdrawn from the fuel assembly in order to control the excess reactivity and thus the location, speed and shape of the burnfront. Controlling location, speed and shape of the burnfront manages neutron fluence seen by fuel assembly structural materials in order to reduce risk of temperature and irradiation damage to the structural materials.

An improved nuclear fission reactor of the liquid metal cooled type including a core configuration allowing for only two operational states, “On” or “Off”, therefore bi-stable. The flow of the primary cooling fluid suspends the core in the “On” state, with sufficient flow to remove the heat to an intermediate heat exchanger during normal operation. This invention utilizes the force of gravity to shut down the reactor after any loss of coolant flow, either a controlled reactor shut down or a “LOCA” event, as the core is controlled via dispersion of fuel elements. Electromagnetic pumps incorporating automatic safety electrical cut-offs are employed to shutdown the primary cooling system to disassemble the core to the “Off” configuration in a situation of a loss of secondary coolant. This design is a hybrid pool-loop unpressurized reactor unique in its use of a minimum number of components, utilizing no moving mechanical parts, no seals, optimized piping, and no control rods, defining an elegantly simple intrinsically safe nuclear reactor.

This invention uses existing technology in a novel way to create a production facility, which can be known as Synergy City, to provide a solution to three problems confronting the United States, and other nations as well: the need for safe, clean, renewable sources of electrical power; the need for adequate supplies of fresh water; and the need to dispose of trash in a responsible manner. A synergistic solution to these problems is presented without the use of nuclear fission, coal or oil.A prototype of Synergy Cities is conceived in which reside scientists, engineers, technicians and their families, and others as necessary to support a viable American city in the state in which it is located. Experience in planning, developing and operating the prototype facility is to be factored into the design and construction of succeeding cities. Such cities can become man-made oases in areas of our country which are presently largely uninhabitable and non-productive, enhancing the environment in which they are located and providing employment opportunities for large numbers of highly technical, as well as non-technical workers.

A traveling wave nuclear fission reactor, fuel assembly, and a method of controlling burnup therein. In a traveling wave nuclear fission reactor, a nuclear fission reactor fuel assembly comprises a plurality of nuclear fission fuel rods that are exposed to a deflagration wave burnfront that, in turn, travels through the fuel rods. The excess reactivity is controlled by a plurality of movable neutron absorber structures that are selectively inserted into and withdrawn from the fuel assembly in order to control the excess reactivity and thus the location, speed and shape of the burnfront. Controlling location, speed and shape of the burnfront manages neutron fluence seen by fuel assembly structural materials in order to reduce risk of temperature and irradiation damage to the structural materials.

A filter type trapping agent for volatile cesium compound and trapping method for volatile cesium compound thereof are provided. More particularly, a filter type trapping agent for volatile cesium compound including silica 40˜65% by weight of silica, 15˜30% by weight of alumina, 5˜15% by weight of iron oxide, 1˜15% by weight of molybdenum oxide, 1˜10% by weight of chromium oxide, and 1˜10% by weight of vanadium oxide and trapping method for volatile cesium compound thereof are provided. Through a filter type trapping agent for volatile cesium compound and a trapping method, only cesium can be selectively separated among the nuclear fission gases. Accordingly, by disposing only the filter where cesium is trapped, the efficiency of an off-gas process improves, expense for disposing filter wastes decreases, and a cesium isotope of the waste filter can be recycled. Therefore, many forms of cesium compound gas are made insoluble efficiently.

As the material with which a measurement system in a detection apparatus is built, the neutron absorber-loaded polyethylene which considerably slows down and absorbs fast neutrons is replaced by iron or an alloy thereof which have no moderating action but have great ability to reflect fast neutrons. With this design, the neutrons admitted into the solid waste under analysis are not only the fast neutrons that go direct into the solid waste from the neutron generating tubes but also the high-energy neutrons reflected from the measurement system. The probability of incidence of nuclear fissions is sufficiently increased to enhance the sensitivity of measurement.

A dual-cooled nuclear fuel rod and a method of manufacturing the same are provided. The nuclear fuel rod includes an outer cladding tube having a circular cross section, an inner cladding tube having an outer diameter smaller than an inner diameter of the outer cladding tube, and a length longer than the outer cladding tube, and located in parallel in the outer cladding tube, a pellet charged in a space between the outer and inner cladding tubes and generating energy by nuclear fission, and first and second end plugs coupling opposite ends of the outer cladding tube to stepped outer joints formed on outer circumferences of first ends thereof and coupling opposite ends of the inner cladding tube to stepped inner joints formed on inner circumferences of the first ends thereof.

Disclosed are a replaceable fusion core that can be inserted and removed from the core of a nuclear fission reactor, thereby enabling the replacement of materials exposed to neutron flux and reducing outage times and “hybrid reactor, method, and device for improved nuclear fusion reactors to provide sufficient flux of fast neutrons with sufficient energy to transmutate transuranic wastes from nuclear fission and to be used in improved nuclear fuel cycles so as to effectively reduce the amount radio-toxicity, and the risks and costs of the disposal of nuclear waste, thereby reducing the cost of nuclear energy and increasing its acceptability as an energy source. This abstract is intended for use as a scanning tool only and is not intended to be limiting.

The invention discloses an underground nuclear plant with nuclear island cavern groups distributed in a gallery shape. The underground nuclear plant comprises nuclear islands used for generating steam through nuclear fission energy and arranged in underground cavern groups, a reactor factory building cavern used for containing reactor factory buildings is arranged in the middle, and auxiliary cavern groups used for containing auxiliary factory buildings are oppositely arranged on the two sides of the reactor factory building cavern to form a gallery structure. The factory buildings of the nuclear islands are distributed underground to form the gallery structure, so that the number of caverns of the cavern groups of the underground nuclear islands can be reduced, adverse stratum directions and ground stress large principal stress directions are conveniently avoided, and stability of surrounding rock of the caverns is facilitated.

The invention belongs to the technical field of nuclear power heat supply, and particularly relates to a large-size commercial nuclear power unit based heat and power cogeneration method. The heat and power cogeneration method includes: using energy generated by nuclear fission to a heat a circular flow coolant in a first loop of a nuclear power plant; heating water in a second loop of the nuclear power plant into steam; and allowing part of steam to push a steam turbine to generate power; extracting the other part of steam from the steam turbine to supply heat. The technical problem of environment pollution due to the conventional coal and gas heating plants can be avoided; bled steam from the nuclear power plant is used for providing heat, and then the problem of environment pollution due to the conventional coal and gas heating plants can be prevented; four loops are arranged from the radioactive first loop system of the nuclear power plant to a regional heat supply network user, reasonable radioactive monitoring is performed, and radioactive matters can be prevent from be released to the heat supply network user.