Calculation method for effective tritium breeding ratio of fusion reactor tritium self-sustaining breeding cladding

Abstract

The invention discloses a method for calculating the effective tritium breeding ratio of a fusion reactor tritium self-sustaining breeding blanket. The method comprises the steps that a physical target and an engineering target of fusion reactor tritium self-sustaining are determined; establishing a cladding model, and carrying out neutronics calculation to obtain neutron thermal deposition and distribution results of the cladding model; calculating to obtain a temperature field and a distribution result based on the cladding model, the neutron thermal deposition and the distribution result; according to the obtained temperature field and the distribution result, obtaining an effective tritium release temperature zone of the cladding model, counting the area or volume of the effective tritium release temperature zone, and calculating the effective tritium release amount of the cladding model; calculating the total effective tritium release amount of the fusion reactor according to the effective tritium release amount of the cladding model; the effective tritium breeding ratio is calculated and compared with the theoretical total tritium breeding ratio, and the fusion reactor tritium self-sustaining capacity is judged. According to the invention, actual releasable tritium is quantified for the first time, and a real and reliable basis is provided for cladding design; the method can be directly used for cladding design optimization of major fusion devices such as ITER, CFETR and the like.

Description

Technical Field

[0001] This invention relates to a method for calculating the effective tritium breeding ratio of a tritium self-sustaining breeding blanket in a fusion reactor, belonging to the field of fusion reactor engineering design. Background Technology

[0002] Nuclear fusion energy is one of the core directions of the future global clean energy system. Its commercial application depends on engineering breakthroughs in fusion reactors, and breeder blanket technology is a key technology for achieving tritium self-sufficiency in fusion reactors. The core functions of the breeder blanket include two aspects: first, generating tritium by bombarding the internal breeder material (such as Li4SiO4) with neutrons; and second, shielding part of the neutron radiation and achieving thermal conversion. Among these, the tritium production capacity is the key to determining the tritium self-sufficiency of the fusion reactor, and its core evaluation index is the total tritium breeding ratio (TBR), traditionally defined as "theoretical total tritium production from the blanket / total tritium consumed by core plasma combustion," and the industry generally requires a TBR ≥ 1.05 to meet the tritium self-sufficiency criticality requirement. Currently, the calculation and evaluation of blanket TBR both domestically and internationally are based on "theoretical total production": using neutronics numerical simulation software (such as MCNP), combined with the structural materials of the blanket (such as low-activation steel RAFM), breeder, and neutron multiplier (such as Be and Li4SiO4&Be). 12 The theoretical TBR of the cladding was calculated based on the Ti) ratio scheme and compared with the critical value of 1.05 to determine whether the tritium self-sufficiency requirement was met.

[0003] However, this method has a fundamental flaw: it cannot reflect the actual availability of tritium in engineering practice.

[0004] (1) The effective release efficiency of tritium was not considered: Due to the non-uniform temperature field inside the blanket, tritium can only be released efficiently online in a specific temperature range (such as 400-800℃); tritium outside this temperature range cannot be released in time and cannot be used by the reactor core, resulting in the theoretical TBR being much higher than the TBR corresponding to the actual usable tritium.

[0005] (2) Theoretical value is out of sync with actual value: Traditional TBR only relies on the material ratio scheme for calculation, without considering the release characteristics and transport loss of tritium in the blanket, which leads to an overestimation of the actual tritium supply capacity of the blanket. This may cause the tritium self-sufficiency evaluation to be distorted. Even if the theoretical TBR is ≥1.05, the actual available tritium may still not meet the core requirements, affecting the steady-state operation of the fusion reactor.

[0006] Furthermore, although existing blanket technology research has progressed from the theoretical stage to the engineering design stage (such as the ITER International Thermonuclear Experimental Reactor and the Chinese CFETR fusion reactor, both of which have carried out breeder blanket design), none of them have established a correlation mechanism between effective tritium release and TBR evaluation: they only use theoretical TBR as the basis for blanket design and tritium self-sufficiency judgment, and have not constructed scientific evaluation indicators for effective tritium release, resulting in blanket schemes that cannot truly match the engineering requirements of tritium self-sufficiency in fusion reactors.

[0007] In summary, the traditional TBR definition and calculation method based on theoretical total production does not take into account the effective release characteristics of tritium, and therefore cannot provide a scientific and accurate evaluation basis for tritium self-sufficiency in fusion reactors. Summary of the Invention

[0008] To address the problems existing in the prior art, this invention provides a method for calculating the effective tritium breeding ratio of a tritium self-sustaining breeding blanket in a fusion reactor.

[0009] To achieve the above objectives, this invention employs a method for calculating the effective tritium breeding ratio of a self-sustaining breeding blanket in a fusion reactor, comprising the following steps:

[0010] Establish the physical and engineering goals for tritium self-sufficiency in fusion reactors;

[0011] A blanket model was established, neutronographic calculations were performed, and the neutron thermal deposition and distribution results of the blanket model were obtained; based on the blanket model and the neutron thermal deposition and distribution results, the temperature field and distribution results were calculated.

[0012] Based on the obtained temperature field and distribution results, the effective tritium release temperature zone of the blanket model is obtained and its area or volume is statistically analyzed, and the effective tritium release amount of the blanket model is calculated.

[0013] The total effective tritium release of the fusion reactor is calculated based on the effective tritium release of the blanket model;

[0014] The effective tritium breeding ratio is calculated and compared with the theoretical total tritium breeding ratio to determine the tritium self-sufficiency of the fusion reactor.

[0015] As an improvement, the establishment of the physical and engineering goals for tritium self-sufficiency in fusion reactors specifically includes:

[0016] Physical Objective: Based on the tritium self-sufficiency assessment requirements, the total effective tritium produced by all breeder blanket modules must meet the requirements for steady-state operation of deuterium-tritium fusion. The critical threshold is TBR ≥ 1.05. Based on this critical value, the tritium consumption T required for steady-state operation of the core plasma is calculated. 消耗 ;

[0017] Project objective: To designate 75% of the inner surface of the fusion reactor vacuum chamber to accommodate N breeder blanket modules, and to reserve 25% of the inner surface for divertors and functional windows; where N is determined by the radius of the vacuum chamber.

[0018] As an improvement, the establishment of the blanket model, the performance of neutronics calculations, and the acquisition of neutron thermal deposition and distribution results of the blanket model specifically include:

[0019] The cladding module in the window region of the vacuum chamber equator was selected, and its cladding region containing a single-layer cold tube was extracted as the cladding model. The cladding model was simulated based on the neutron Monte Carlo software MCNP, and the neutron thermal deposition dose and distribution data were output.

[0020] The cladding model employs a solid ceramic structure, with low-activation steel as the structural material, Li4SiO4 as the multiplier, and Be and Li4SiO4&Be as the neutron multipliers. 12 Ti.

[0021] As an improvement, the calculation of the temperature field and distribution results based on the blanket model, neutron thermal deposition, and distribution results specifically includes:

[0022] The blanket model was imported into the ANSYS CFD module, and the neutron thermal deposition and distribution results were used as input data. The blanket temperature field and distribution results were obtained through finite element calculation.

[0023] As an improvement, the step of obtaining the effective tritium release temperature zone of the blanket model based on the obtained temperature field and distribution results, and statistically analyzing its area or volume, and calculating the effective tritium release amount of the blanket model, specifically includes:

[0024] First, using ANSYS CFD post-processing technology, the isotherm-enclosed region in the cladding temperature field that facilitates effective tritium release is extracted, and the two-dimensional area A of this region is statistically analyzed. j Or three-dimensional volume V j ;

[0025] Then, combining the tritium production ratio calculated by MCNP, the effective tritium release of the cladding model is calculated:

[0026] In a two-dimensional scene, T 模型释放 =∑(n i ×A j );

[0027] In a 3D scene, T 模型释放 =∑(N i ×V j );

[0028] Where ∑ represents the summation; n i Tritium productivity per unit area; A j The two-dimensional area of ​​the tritium release temperature zone; N i Productivity per unit volume of tritium; V j The three-dimensional volume of the tritium release temperature zone.

[0029] As an improvement, the calculation of the total effective tritium release of the fusion reactor based on the effective tritium release of the blanket model specifically includes:

[0030] First, calculate the effective tritium release T of a single cladding module. 模块释放 = n L ×T 模型释放 , where n L To determine the number of cold pipe layers in the cladding module, set the equatorial window module n. L It is a constant value;

[0031] Then calculate the total effective tritium release T in the 75% vacuum chamber surface area. 总释氚 = N×T 模块释放 N represents the number of proliferation blanket modules.

[0032] As an improvement, the calculation of the effective tritium breeding ratio and comparison with the theoretical total tritium breeding ratio to determine the tritium self-sufficiency of the fusion reactor specifically includes:

[0033] Calculate the effective tritium breeding ratio (TBR) 有效 = T 总释氚 / T 消耗 ;

[0034] The theoretical total tritium breeding ratio (Net TBR) is calculated as: Net TBR = Local TBR × [75% × (1-Li%)], where Net TBR is the theoretical total tritium breeding ratio; Local TBR is the tritium breeding ratio of a single blanket model; and Li% is the tritium breeding ratio under a given neutron wall load (in MW / m²). 2 The percentage of total lithium atoms burned after two years of irradiation.

[0035] If TBR is satisfied 有效 If ≥Net TBR≥1.05, then the fusion reactor can be determined to be tritium self-sufficient.

[0036] A second aspect of the present invention also provides a calculation apparatus for the effective tritium breeding ratio of a breeding blanket for tritium self-sufficiency in a fusion reactor, for implementing the aforementioned calculation method for the effective tritium breeding ratio of a breeding blanket for tritium self-sufficiency in a fusion reactor, comprising:

[0037] The target module is used to establish the physical and engineering goals for tritium self-sufficiency in fusion reactors;

[0038] The model building and simulation calculation module is used to establish the blanket model, perform neutronics calculations, and obtain the neutron thermal deposition and distribution results of the blanket model; based on the blanket model and the neutron thermal deposition and distribution results, the temperature field and distribution results are calculated.

[0039] The temperature zone acquisition and calculation module is used to obtain the effective tritium release temperature zone of the blanket model based on the obtained temperature field and distribution results, and to calculate its area or volume, and calculate the effective tritium release amount of the blanket model.

[0040] The total tritium release calculation module is used to calculate the total effective tritium release of the fusion reactor based on the effective tritium release of the blanket model.

[0041] The determination module is used to calculate the effective tritium breeding ratio and compare it with the theoretical total tritium breeding ratio to determine the tritium self-sufficiency of the fusion reactor.

[0042] A third aspect of the present invention also provides an iterative computing device, comprising:

[0043] processor;

[0044] The memory is used to store processor-executable instructions;

[0045] The processor is used to run computer programs or instructions to implement the method for calculating the effective tritium breeding ratio of the breeding blanket for tritium self-sustaining fusion reactors.

[0046] In a fourth aspect, the present invention also provides a computer-readable storage medium storing computer-executable instructions, which, when executed by a processor, are used to implement the method for calculating the effective tritium breeding ratio of the breeding blanket for tritium self-sustaining fusion reactors.

[0047] Mechanism of the invention:

[0048] A critical baseline of "effective TBR ≥ 1.05" (covering losses from transportation and storage) is set according to the steady-state operation requirements of the fusion reactor. The actual tritium consumption T is calculated based on the core plasma parameters. 消耗 This invention determines the amount of effective tritium required for the blanket by working backward from the amount of tritium needed in the reactor core, aligning with engineering requirements. It utilizes MCNP to obtain the local tritium breeding ratio (Local TBR), tritium production ratio (ni / Ni), and neutron thermal deposition distribution of the blanket, clarifying the tritium production potential and heat generation distribution characteristics of the blanket. The tritium production ratio × effective temperature zone area / volume (∑(n...)) is used to... i ×A j ) or ∑(N) i ×V j )) Calculate T 模型释放 This is the first time that theoretical tritium production has been transformed into practically releaseable tritium, filling an engineering gap in traditional methods.

[0049] Compared with the prior art, the beneficial effects of the present invention are:

[0050] (1) Traditional methods only calculate the theoretical TBR based on the material ratio, without considering the effect of temperature on tritium release, which leads to an overestimation of the actual capability (e.g., theoretical TBR ≥ 1.05, but actual effective TBR < 1.05). This invention quantifies the actual releaseable tritium for the first time, providing a real and reliable basis for cladding design.

[0051] (2) Traditional full-reactor TBR calculation requires traversing all modules, resulting in a huge amount of computation (taking several weeks). This invention shortens the calculation cycle by combining typical modules and equivalent conversions. At the same time, due to the representativeness of the equatorial module, the calculation accuracy is no less than that of direct full-reactor calculation, which greatly improves the R&D efficiency of fusion reactor blanket design and reduces time costs.

[0052] (3) This invention derives the blanket design requirements from the core tritium demand. By using the effective TBR, the blanket design defects can be directly traced (such as an insufficient effective temperature range → requiring adjustment of the cooling structure or material ratio), forming a closed loop of target setting, model calculation, result feedback, and design optimization. For example, if the effective TBR < 1.05, improvements can be made by expanding the 400-800℃ temperature range (adjusting the cold tube layout) or increasing the tritium production ratio (optimizing the proportion of Li4SiO4), providing a clear direction for blanket engineering design.

[0053] (4) Tritium self-sufficiency is the core bottleneck of fusion reactor commercialization. The effective TBR calculation method provided by this invention can be directly used for the blanket design optimization of major fusion devices such as ITER and CFETR: avoiding blanket rework caused by misjudgment due to traditional methods (such as theoretically meeting the standard but actually being unable to self-sufficiency); accelerating the engineering implementation of the blanket (providing quantifiable and verifiable design indicators); providing scientific support for the tritium fuel cycle of fusion reactor grid-connected power generation, and helping nuclear fusion move from experimental devices to clean energy power plants.

[0054] (5) The method for calculating the effective tritium breeding ratio proposed in this invention, with its original core ideas, technical approaches and key implementation paths, has opened up a new research direction for theoretical innovation and technological development of fusion blankets and constructed a differentiated calculation system. On the one hand, this method promotes the refinement and upgrading of statistical calculation methods for tritium production in fusion reactors and improves the logic of tritium production quantification; on the other hand, it promotes breakthroughs in the transient numerical simulation technology of blanket thermal nonlinearity and optimizes the simulation accuracy of temperature field and tritium release coupling; at the same time, it accelerates the construction of a scientific system for evaluating the effectiveness of blanket tritium, fills the gap in traditional evaluation based solely on theoretical tritium production, provides systematic technical support for the engineering design of fusion blankets, and unites scientific research and engineering forces to continuously promote breakthroughs in tritium self-sufficiency technology in fusion reactors. Attached Figure Description

[0055] Figure 1 This is the position of the cladding model of the present invention in the cladding structure (single-layer cold pipe).

[0056] Figure 2 This is a diagram showing the nuclear heat dose and distribution of the cladding model of the present invention; wherein, the vertical axis represents nuclear heat (W / cm3) and the horizontal axis represents the radial direction (mm).

[0057] Figure 3 This is a temperature field distribution diagram of the cladding model of the present invention;

[0058] Figure 4 This is a diagram showing the isothermal region division of the blanket model of the present invention; in the diagram, Neutrons, 2D blanket model, Cooling pipe, Breeder area, Isothem at 400℃, Poloidal direction, and Radial direction are also represented.

[0059] Figure 5 This is a temperature distribution map showing the effective release temperature range of tritium in the coating model of this invention. Detailed Implementation

[0060] The following embodiments are further illustrations of the present invention and serve as explanations of the technical content of the present invention. However, the essence of the present invention is not limited to the embodiments described below. Those skilled in the art can and should know that any simple changes or substitutions based on the spirit of the present invention should fall within the protection scope claimed by the present invention.

[0061] Example 1

[0062] A method for calculating the effective tritium breeding ratio of a breeding blanket for tritium self-sustaining fusion reactors includes the following steps:

[0063] S1. Establish the physical and engineering goals for tritium self-sufficiency in fusion reactors.

[0064] Physical Objective: Based on the tritium self-sufficiency assessment requirements, the total effective tritium produced by all breeder blanket modules must meet the steady-state operation requirements of the deuterium-tritium fusion reaction. The critical benchmark is a total tritium breed ratio (TBR) ≥ 1.05 (this value already covers actual losses such as tritium transport leakage and storage decay). Based on this critical benchmark, the tritium consumption T required for steady-state operation of the core plasma is calculated. 消耗 ;

[0065] Project objective: To design N breeder blanket modules to be arranged on 75% of the inner surface of the fusion reactor vacuum chamber, and to reserve space for divertors, functional windows and tritium production compensation design on 25% of the inner surface; where N is determined by the large radius of the vacuum chamber, the larger the radius, the larger the inner surface area of ​​the vacuum chamber, and the more blanket modules need to be installed on the inner surface of the vacuum chamber.

[0066] S2. Establishing a neutronics model for the breeding blanket.

[0067] Select the window region in the equatorial region of the vacuum chamber (withstanding a neutron wall load of 3MW / m). 2 (This is the region with the strongest neutron irradiation and the most typical tritium production in the entire reactor), and its cladding region containing a single layer of cold pipes is taken as the cladding model, such as... Figure 1 As shown; the cladding model adopts a solid ceramic structure, the structural material is low-activation steel (RAFM, ​​used for cladding and first wall manufacturing), the multiplier is Li4SiO4 (in solid particle form), and the neutron multiplier is Be and Li4SiO4&Be. 12 Ti; A three-dimensional cladding structure model is constructed using CAD software and imported into the Monte Carlo neutronics calculation software MCNP to form a neutronics model that can be used for numerical simulation.

[0068] S3, Neutronics Calculations and Temperature Field Simulation

[0069] Neutronics calculations: The blanket model was simulated globally using MCNP software. The input neutron source parameters were high-energy neutrons produced by the deuterium-tritium reaction. Three key results were output: Local Tritium Breeding Ratio (Local TBR, i.e., the tritium breeding ratio of a single blanket model), and tritium production rate distribution (including tritium production rate per unit area ni, unit: kg / (m²)). 2 •s); Tritium productivity per unit volume, Ni, unit: kg / (m³) 3 ·s), neutron thermal deposition distribution (covering the entire first wall, breeding zone, and cooling channel, with data spatial resolution matching the mesh accuracy of subsequent temperature field simulations), such as Figure 2 As shown;

[0070] Temperature field simulation: The above neutron thermal deposition distribution results were used as input data and imported into the CFD module of the finite element software ANSYS. A steady-state heat transfer model (pressurized water reactor cooling conditions, such as inlet 290℃ and outlet 330℃) was adopted. Through finite element calculation, the temperature field distribution map of the entire blanket was obtained, as shown below. Figure 3 As shown;

[0071] S4. Determine the effective tritium release temperature range.

[0072] Using ANSYS CFD post-processing technology, the isotherm region surrounding 400-800℃ in the cladding temperature field was extracted (this temperature range was determined based on the diffusion coefficient of tritium in Li4SiO4 ≥ 1 × 10⁻⁶). -10 m 2 / s, which ensures efficient online tritium release, such as Figure 4 , Figure 5 As shown; calculate the two-dimensional area of ​​this region (denoted as A). j Unit: m 2 ) or three-dimensional volume (denoted as V)j Unit: m 3 ), where j is the effective temperature zone number (values ​​are 1, 2, ..., n; n is the total number of effective temperature zones, determined according to the actual distribution of the temperature field);

[0073] S5. Calculate the effective tritium release.

[0074] Based on the tritium production ratio calculated by MCNP, the effective tritium release of the cladding model is calculated:

[0075] In a two-dimensional scene, T 模型释放 =∑(n i ×A j );

[0076] Where i is the tritium production ratio number (corresponding one-to-one with the effective temperature zone number j), and ∑ represents the summation of ni×Aj over all effective temperature zones;

[0077] In a 3D scene, T 模型释放 =∑(N i ×V j );

[0078] Where ∑ represents N for all effective temperature ranges. i ×V j Summation;

[0079] S6. Calculate the total effective tritium release from the entire stack.

[0080] The effective tritium release of a single cladding module is denoted as T. 模块释放 The calculation formula is T 模块释放 = n L ×T 模型释放 ;

[0081] Where, n L Number of cladding module cold pipe layers (equatorial window module n) L (Set as a fixed value for 3-5 floors).

[0082] Total effective tritium release from the entire reactor: denoted as T 总释氚 The calculation formula is T 总释氚 = N×T 模块释放 Under current technology, it is assumed that the tritium release amount of each cladding module is consistent. When future technology allows, the effective tritium release amount of each of the N cladding modules can be calculated separately and then summed to further reduce calculation errors.

[0083] S7. Calculate the effective tritium proliferation ratio (TBR) 有效 And determined that tritium is self-sustaining

[0084] Effective tritium breeding ratio calculation: denoted as TBR 有效 The calculation formula is TBR 有效 = T总释氚 / T 消耗 ;

[0085] Theoretical total tritium proliferation ratio calculation: denoted as Net TBR, the calculation formula is Net TBR = Local TBR × [75% × (1-Li%)];

[0086] Where Net TBR is the theoretical total tritium breeding ratio, and Li% is the value of the tritium load at a given neutron wall (in MW / m²). 2 The percentage of total lithium atoms burned after two years of irradiation.

[0087] Tritium self-sufficiency criterion: If TBR is satisfied 有效 If ≥Net TBR≥1.05, then the fusion reactor can be determined to be tritium self-sufficient;

[0088] S8. Determine the effective tritium proliferation ratio.

[0089] Two-dimensional scene: TBR 有效 =(N×n L ×∑(n i ×A j )) / T 消耗 ;

[0090] 3D Scene: TBR 有效 =(N×n L ×∑(N i ×V j )) / T 消耗 .

[0091] Example 2

[0092] A calculation device for the effective tritium breeding ratio of a breeding blanket for tritium self-sustaining fusion reactors, used to implement the above-mentioned calculation method for the effective tritium breeding ratio of a breeding blanket for tritium self-sustaining fusion reactors, includes:

[0093] Target setting module: used to clarify the physical and engineering goals of tritium self-sufficiency in fusion reactors, define the tritium self-sufficiency critical benchmark and the calculation basis for core tritium consumption;

[0094] Modeling and Dual-Field Simulation Module: Used to construct the blanket model, obtain neutron thermal deposition and distribution data of the blanket model through neutronics calculations; based on the model and neutron thermal deposition and distribution data, the temperature field and distribution results are simulated.

[0095] Effective temperature zone and tritium release calculation module: Based on the temperature field and distribution results, it extracts the effective tritium release temperature zone of the blanket model and calculates its area or volume, and calculates the effective tritium release of the blanket model in combination with the tritium production ratio;

[0096] Total Tritium Release Calculation Module: Used to calculate the effective tritium release based on the blanket model, and then convert it into the total effective tritium release of the fusion reactor.

[0097] Tritium self-sufficiency determination module: used to calculate the effective tritium breeding ratio and compare it with the theoretical total tritium breeding ratio to determine the tritium self-sufficiency capability of the fusion reactor.

[0098] Example 3

[0099] An iterative computing device (small workstation) includes:

[0100] processor;

[0101] The memory is used to store processor-executable instructions;

[0102] The processor is configured to execute the computer-executable instructions to implement the above-mentioned method for calculating the effective tritium breeding ratio of the breeding blanket for tritium self-sufficiency in fusion reactors. By supporting blanket neutronics calculations, temperature field simulations, and tritium breeding ratio quantitative analysis with high-efficiency computing power, it significantly improves the accuracy and efficiency of determining the tritium self-sufficiency capability of fusion reactors and provides core hardware support for the optimization of blanket engineering design.

[0103] A computer-readable storage medium stores computer-executable instructions. When executed by a processor, the computer-executable instructions can realize the above-mentioned method for calculating the effective tritium breeding ratio of the breeding blanket for tritium self-sufficiency in fusion reactors. This provides reliable data storage and execution guarantees for the stable deployment, cross-platform promotion, and engineering application of this original technical solution, and accelerates the research and development iteration and industrial transformation of tritium self-sufficiency technology in fusion reactors.

[0104] The above description is only a preferred embodiment of the present invention and is not intended to limit the present invention. Any modifications, equivalent substitutions or improvements made within the spirit and principles of the present invention should be included within the protection scope of the present invention.

Claims

1. A method for calculating the effective tritium breeding ratio of a breeding blanket for tritium self-sustaining fusion reactors, characterized in that, Includes the following steps: Establish the physical and engineering goals for tritium self-sufficiency in fusion reactors; A blanket model was established, neutronographic calculations were performed, and the neutron thermal deposition and distribution results of the blanket model were obtained; based on the blanket model and the neutron thermal deposition and distribution results, the temperature field and distribution results were calculated. Based on the obtained temperature field and distribution results, the effective tritium release temperature zone of the blanket model is obtained and its area or volume is statistically analyzed, and the effective tritium release amount of the blanket model is calculated. The total effective tritium release of the fusion reactor is calculated based on the effective tritium release of the blanket model; The effective tritium breeding ratio is calculated and compared with the theoretical total tritium breeding ratio to determine the tritium self-sufficiency of the fusion reactor.

2. The method for calculating the effective tritium breeding ratio of a tritium self-sustaining breeding blanket in a fusion reactor according to claim 1, characterized in that, The established physical and engineering goals for tritium self-sufficiency in fusion reactors specifically include: Physical Objective: Based on the tritium self-sufficiency assessment requirements, the total effective tritium produced by all breeder blanket modules must meet the requirements for steady-state operation of deuterium-tritium fusion. The critical threshold is TBR ≥ 1.

05. Based on this critical value, the tritium consumption T required for steady-state operation of the core plasma is calculated. 消耗 ; Project objective: To designate 75% of the inner surface of the fusion reactor vacuum chamber to accommodate N breeder blanket modules, and to reserve 25% of the inner surface for divertors and functional windows; where N is determined by the radius of the vacuum chamber.

3. The method for calculating the effective tritium breeding ratio of a self-sustaining tritium breeding blanket in a fusion reactor according to claim 1, characterized in that, The establishment of the blanket model, the performance of neutronographic calculations, and the acquisition of neutron thermal deposition and distribution results of the blanket model specifically include: The cladding module in the window region of the vacuum chamber equator was selected, and its cladding region containing a single-layer cold tube was extracted as the cladding model. The cladding model was simulated based on the Monte Carlo neutron calculation software MCNP, and the neutron thermal deposition dose and distribution data were output. The cladding model employs a solid ceramic structure, with low-activation steel as the structural material, Li4SiO4 as the multiplier, and Be and Li4SiO4&Be as the neutron multipliers. 12 Ti.

4. The method for calculating the effective tritium breeding ratio of a tritium self-sustaining breeding blanket in a fusion reactor according to claim 1, characterized in that, The temperature field and distribution results calculated based on the blanket model, neutron thermal deposition, and distribution results specifically include: The blanket model was imported into the ANSYS CFD module, and the neutron thermal deposition and distribution results were used as input data. The blanket temperature field and distribution results were obtained through finite element calculation.

5. The method for calculating the effective tritium breeding ratio of a tritium self-sustaining breeding blanket in a fusion reactor according to claim 1, characterized in that, The process of obtaining the effective tritium release temperature zone of the blanket model based on the obtained temperature field and distribution results, calculating its area or volume, and then calculating the effective tritium release amount of the blanket model specifically includes: First, using ANSYS CFD post-processing technology, the isotherm-enclosed region in the cladding temperature field that facilitates effective tritium release is extracted, and the two-dimensional area A of this region is statistically analyzed. j Or three-dimensional volume V j ; Then, combining the tritium production ratio calculated by MCNP, the effective tritium release of the cladding model is calculated: In a two-dimensional scene, T 模型释放 =∑(n i ×A j ); In a 3D scene, T 模型释放 =∑(N i ×V j ); Where ∑ represents the summation; n i Tritium productivity per unit area; A j The two-dimensional area of ​​the tritium release temperature zone; N i Productivity per unit volume of tritium; V j The three-dimensional volume of the tritium release temperature zone.

6. The method for calculating the effective tritium breeding ratio of a tritium self-sustaining breeding blanket in a fusion reactor according to claim 1, characterized in that, The calculation of the total effective tritium release of the fusion reactor based on the effective tritium release from the blanket model specifically includes: First, calculate the effective tritium release T of a single cladding module. 模块释放 = n L ×T 模型释放 , where n L To determine the number of cold pipe layers in the cladding module, set the equatorial window module n. L It is a constant value; Then calculate the total effective tritium release T in the 75% vacuum chamber surface area. 总释氚 = N×T 模块释放 N represents the number of proliferation blanket modules.

7. The method for calculating the effective tritium breeding ratio of a tritium self-sustaining breeding blanket in a fusion reactor according to claim 1, characterized in that, The calculation of the effective tritium breeding ratio and comparison with the theoretical total tritium breeding ratio to determine the tritium self-sufficiency of the fusion reactor specifically includes: Calculate the effective tritium breeding ratio (TBR) 有效 = T 总释氚 / T 消耗 ; The theoretical total tritium breeding ratio (Net TBR) is calculated as: Net TBR = Local TBR × [75% × (1-Li%)], where Net TBR is the theoretical total tritium breeding ratio; Local TBR is the tritium breeding ratio of a single blanket model; and Li% is the percentage of total lithium atoms burned after two years of irradiation under a given neutron wall load. If the TBR is satisfied... 有效 If ≥Net TBR≥1.05, then the fusion reactor can be determined to be tritium self-sufficient.

8. A calculation device for the effective tritium breeding ratio of a breeding blanket for tritium self-sustaining fusion reactors, characterized in that, A method for calculating the effective tritium breeding ratio of a self-sustaining breeding blanket for a fusion reactor as described in any one of claims 1-7, comprising: The target module is used to establish the physical and engineering goals for tritium self-sufficiency in fusion reactors; The model building and simulation calculation module is used to establish the blanket model, perform neutronics calculations, and obtain the neutron thermal deposition and distribution results of the blanket model; based on the blanket model and the neutron thermal deposition and distribution results, the temperature field and distribution results are calculated. The temperature zone acquisition and calculation module is used to obtain the effective tritium release temperature zone of the blanket model based on the obtained temperature field and distribution results, and to calculate its area or volume, and calculate the effective tritium release amount of the blanket model. The total tritium release calculation module is used to calculate the total effective tritium release of the fusion reactor based on the effective tritium release of the blanket model. The determination module is used to calculate the effective tritium breeding ratio and compare it with the theoretical total tritium breeding ratio to determine the tritium self-sufficiency of the fusion reactor.

9. An iterative computing device, characterized in that, include: processor; The memory is used to store processor-executable instructions; The processor is used to run computer programs or instructions to implement the method for calculating the effective tritium breeding ratio of the breeding blanket for tritium self-sufficiency in a fusion reactor as described in any one of claims 1-7.

10. A computer-readable storage medium, characterized in that, The computer-readable storage medium stores computer-executable instructions, which, when executed by a processor, are used to implement the method for calculating the effective tritium breeding ratio of a self-sustaining breeding blanket for a fusion reactor as described in any one of claims 1-7.

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