A Design Method of Fusion Blanket for Controlling the Tritium Release Effectiveness

Abstract

The present invention discloses a method for designing a fusion blanket to control the effectiveness of tritium release. By designing the temperature field distribution of the blanket through materials and then calculating the actual TBR of the blanket, a scientific and technological approach for obtaining an optimized blanket design scheme is achieved. Among them, the MCNP software, ANSYS software, and a method of neutron detection spheres are used to assist the entire process of blanket design. The present invention is based on adjusting the material proportion and position of each region inside the blanket to achieve the balance of the temperature field, and at the same time referring to the requirement of the optimal temperature range for effective tritium release. By using a method of neutron detection spheres, the actual tritium release dose and its distribution are obtained, and then the actual TBR is statistically calculated. Finally, an advanced blanket design scheme is obtained, providing a scientific basis for the realization of the blanket engineering of future fusion reactors. Based on the content described in the present invention, the designed fusion reactor blanket can have the function of producing tritium stably and effectively, thus strongly supporting the construction of future fusion reactors and providing clean energy for humanity.

Description

Technical Field

[0001] The present invention relates to the field of fusion reactor engineering design, and particularly to a design method for a fusion blanket to control the effectiveness of tritium release. Background Art

[0002] In order to address the future global energy crisis, many countries in the world have been actively building large-scale fusion devices in recent years to carry out relevant research in the field of fusion energy technology. For example, the non-circular cross-section fully superconducting tokamak EAST device built in Hefei, China, the JT-60 in Japan, the KSTAR in South Korea, and the ITER experimental reactor device built in France.

[0003] The research on fusion blanket design technology mainly focuses on carrying out relevant theoretical and engineering research work to meet the actual needs of the future fusion reactor's tritium fuel self-sustaining cycle. The main function of the blanket is to produce tritium. The fusion blanket design method mainly carries out relevant work based on the physical objectives and requirements of the fusion reactor. The future fusion reactor needs to generate fusion energy in the form of a commercial reactor to provide clean energy for humanity. The fusion reactor must be able to carry out a steady-state and long-term deuterium-tritium reaction, and tritium is the main fuel to maintain the core fusion reaction. One of the physical objectives of the fusion reactor requires that its important functional component, the breeding blanket, can produce kilograms of tritium during operation to maintain its combustion in the fusion reactor core. Since the fusion reaction itself produces neutrons, when the neutrons enter the first wall of the functional component blanket and strike the internal breeding material inside, tritium is generated. At the same time, the blanket has a neutron multiplication function. In this way, the entire blanket continuously uses the neutrons from the reactor core, its own multiplied neutrons, and the breeding material to produce tritium reactions, thereby producing a continuous supply of tritium, and the tritium is then supplied to the core fusion reaction through the transport system. The fusion reactor requires that the tritium-producing blanket can achieve the self-sustaining effectiveness of tritium production. The technical index for judging whether tritium can achieve self-sustaining requirements in the field of fusion reactor technology is that the blanket TBR is greater than 1.

[0004] The blanket design initially focused on conceptual design and has gradually tended to engineering design. In terms of types, the blanket design is divided into solid blankets and liquid blanket designs. The solid blanket is further divided into two forms: helium-cooled blanket and water-cooled blanket according to different cooling media. For the solid blanket design, the current main method is to first design a technical index parameter with a TBR greater than 1 based on the principle of tritium production by neutrons striking the breeder material, and then carry out the design of the proportioning of the blanket structural material and the cooling method according to the influence of the neutron dose on the blanket material under a certain fusion power. Before completing the specific engineering structure design, the neutronics analysis and calculation of the blanket is an important link, that is, to calculate whether the blanket TBR can reach the self-sustaining requirement of being greater than 1. If the calculation result is greater than 1, it is basically considered that this design concept meets the design requirements and the next design activity can be carried out.

[0005] Theoretically speaking, starting from the physical objectives and engineering design requirements of the fusion reactor, through theoretical numerical simulation calculations, accurate calculation results are obtained to guide the design of the engineering structure. This idea is undoubtedly correct. However, after long-term blanket design research, it has been found that there is a common shortcoming in the existing blanket design methods at home and abroad, that is, the obtained TBRs are not the actual TBRs of the blanket, and the tritium release effectiveness after tritium production in the blanket is not taken into account. Therefore, the blanket design results obtained by such fusion blanket design methods cannot ensure the tritium self-sustaining effectiveness during actual tritium production.

[0006] From the current research status of fusion blanket design at home and abroad, blanket designers basically believe that after obtaining a TBR that meets the tritium self-sustaining effectiveness, the further detailed design of the blanket engineering structure can be carried out. The ideas and steps of this fusion blanket design method mainly include: after the blanket model undergoes neutronics calculations and thermal engineering techniques, an optimized structural design is carried out, and then iterative calculations are continued. After determining that the TBR is greater than 1, the final blanket design scheme is finally determined. It can be seen that the entire design process does not mention the important influence of the temperature field distribution on the tritium release effectiveness, and this key factor is the core that affects the actual tritium production of the blanket. Therefore, such design results can be considered to have a large error from the real situation, and the feasibility of the blanket scheme in future projects is also questionable, or at least inaccurate.

[0007] In fact, there is nothing wrong with the calculated TBR being greater than 1 based on the above-mentioned blanket design method. However, there is indeed a problem with the tritium release effectiveness when the blanket actually produces tritium. The sufficiency of tritium release in the blanket is closely related to its internal temperature field and its distribution, that is, there is a problem with the tritium release effectiveness of the blanket. If the tritium release area of the blanket is not in the optimal temperature range, the produced tritium cannot be released fully, and this problem has been seriously ignored by many blanket design researchers.

[0008] The experiments of scientists have shown that the temperature range for effective tritium release is approximately 400 - 800 °C, with the high tritium release points at 480.5 °C and 659 °C. However, due to the presence of cooling pipelines inside the blanket, especially when using water cooling, such as the inlet and outlet conditions of the coolant in a pressurized water reactor being 285 - 325 °C, the temperature in the near-wall region of the water cooling pipes and their pipe walls is significantly lower than 400 °C. Thus, even if tritium is produced, due to the existence of the low-temperature region, a large amount of tritium will concentrate in this region and cannot be effectively released, thereby affecting the calculation of the actual TBR of the blanket. Some scientists believe that if high-temperature purging is used to assist tritium release, such as purging the pebble bed of the blanket at 700 °C, but the safety temperature limit for the softening of the low-activation steel material inside the blanket is 550 °C. Such high-temperature purging poses a threat to the blanket structure. And below 550 °C, for example, 500 °C is relatively close to the first high tritium release point of 480.5 °C and seems possible, but the tritium release temperature range of the blanket is 400 - 800 °C. Solving the tritium release effectiveness problem in all regions inside the blanket cannot be achieved by just one high-temperature point. In this sense, the actual effect of high-temperature purging will be greatly discounted technically. Therefore, new technical approaches must be sought to achieve tritium release effectiveness. Consequently, for a situation where the TBR obtained from the theoretical calculation of a blanket model is greater than 1, the TBR value obtained under actual tritium release may be much lower than this value. Hence, the blanket design schemes designed using existing common design methods need to be corrected by finding more scientific design methods or approaches. Summary of the Invention

[0009] To address the above deficiencies in the current fusion solid blanket design technology, the present invention provides a fusion blanket design method that can achieve the requirement of tritium self-sustainment for the actual TBR, that is, a fusion blanket design method that controls the effectiveness of tritium release.

[0010] When designing the internal structure of the blanket, the present invention achieves the balance of the internal temperature field by adjusting the material proportion and position distribution in each region. The temperature field distribution in the main breeding region conforms to the requirements of the optimal temperature range for effective tritium release, thus playing an important supporting role in the actual tritium release and its effectiveness of the blanket. The specific technical solutions adopted by the present invention are as follows:

[0011] A fusion blanket design method for controlling the effectiveness of tritium release includes the following steps:

[0012] 1) Selection of the blanket structure model:

[0013] According to the design objectives and requirements of the functional component - tritium - producing blanket of the fusion reactor, select a blanket structure model. For example, a solid water - cooled blanket structure form can be selected; the fusion blanket is a tritium - producing functional component, and its design objective is that TBR > 1 to meet the tritium self - sustained combustion of the fusion reactor; its engineering objective is that, excluding uncertain factors such as along - the - way losses and leakage, the effective TBR > 1.

[0014] 2) Cladding material design:

[0015] By adjusting the material proportion and position of each area of the cladding to achieve the balance of the internal temperature field, where the temperature field distribution in the main breeding area meets the requirements of the optimal temperature range for effective tritium release, it thus plays an important supporting role in the actual tritium release and its effectiveness of the cladding. The optimal temperature range for tritium release is 400 - 800 °C. Based on this, the proportion and position of various materials inside the cladding are designed to adapt to the effective tritium release. Among them, the design of the breeding area and the multiplication area inside the cladding satisfies the gradient distribution law of neutrons after entering the cladding from the first wall, and at the same time, the self-melting temperature limit of various materials is considered. The method to achieve the optimal temperature range for effective tritium release is the iterative analysis of neutronics nuclear heat calculation and computational fluid dynamics simulation based on the temperature field distribution of the cladding, obtaining the optimal temperature field distribution under the material design, that is, meeting both the characteristics of neutron heat deposition distribution and the optimal temperature range for effective tritium release and the control of the temperature limit of the cladding material.

[0016] 3) Calculation of the tritium breeding ratio (TBR) of the cladding:

[0017] Based on the neutronics Monte Carlo calculation software MCNP, calculate the TBR value of the cladding, accurate to the hundredth place (0.00);

[0018] 4) Calculation of neutron thermal distribution:

[0019] Based on the neutronics model of the cladding, calculate the neutron heat deposition, and obtain the neutron heat deposition dose and its distribution trend diagram;

[0020] 5) Numerical simulation of the cladding temperature field:

[0021] According to the neutron heat deposition results of the cladding and its distribution area, load them into the fluid dynamics model for finite element simulation calculation to obtain the temperature field distribution results; the cladding temperature field distribution is related to the cladding material design and position, and its control method is regulated through step 2) cladding material design.

[0022] 6) Iterative calculation of the cladding temperature field and TBR:

[0023] Calculate the neutronics model of a cladding design to obtain the TBR value under this model; calculate the cladding temperature field distribution under this model; according to the optimal temperature range for effective tritium release of the cladding, based on the neutronics detection sphere method, statistically calculate the actual tritium release amount and its proportion of the cladding, calculate the corresponding TBR value, and judge whether this cladding design scheme can achieve the self-sustaining effectiveness of tritium; if not, return to step (2) to adjust the material design of each part of the cladding, perform the cladding neutronics analysis again, calculate the TBR, and perform the numerical analysis of the cladding temperature field and the calculation of the actual tritium multiplication ratio in the case of tritium release effectiveness again; use this as the steps and basis for iterative calculation.

[0024] 7) Optimization of the blanket design:

[0025] Based on the TBR obtained from the neutronics calculations in the blanket, the first model optimization is completed. Then, according to the temperature distribution in the blanket, the result of the blanket design is optimized. Based on this design result, the blanket design that meets the conditions for effective tritium release is analyzed. Combining the aforementioned TBR calculation results, the blanket design scheme is optimized.

[0026] The fusion blanket design method of the present invention may include: a model diagram of a fusion blanket design example and a flowchart of a fusion solid-state water-cooled blanket design.

[0027] In the fusion blanket design method of the present invention, the designed blanket scheme can achieve tritium self-sustainability effectiveness in future engineering. Whether the final blanket design is successful needs to be determined from the following aspects: 1) The actual TBR value is greater than 1; 2) The temperature field in the blanket is suitable for effective tritium release (optimal temperature range); 3) The safety of the structure and materials (judged based on the melting temperature limit of the materials).

[0028] In the fusion blanket design method of the present invention, the TBR in step 3) is greater than or equal to 1 to meet the parameter requirements for tritium self-sustainability effectiveness determination.

[0029] In the fusion blanket design method of the present invention, its technical control approach is mainly carried out through two important technical points: the design of the blanket materials and the statistical calculation of the actual TBR. The initial conditions for the design of the blanket material area and ratio are empirical parameters. Then, based on steps such as the TBR of the calculation model, the numerical simulation of the temperature field, and the statistical calculation of the actual tritium release rate within the effective tritium release temperature range, it is completed and fed back to the initial blanket design for iterative calculation to adjust the blanket design process to ensure the optimization of the blanket scheme.

[0030] In the fusion blanket design method of the present invention, the TBR is the result of continuous iterative calculation and optimization during the calculation. The blanket TBR is the result calculated according to a design model of the blanket. The blanket design scheme corresponding to the initial result does not represent the final design scheme. According to the thermal safety requirements of the blanket (the temperature permission limit of the blanket materials) and the fundamental requirements for effective tritium release in the blanket, the blanket design scheme is adjusted and recalculated in a certain order. Such a continuously optimized process is called the iterative calculation process of the blanket scheme.

[0031] In the fusion blanket design method of the present invention, the temperature field distribution map is the result obtained through fluid heat transfer simulation calculation based on the nuclear heat distribution in neutronics calculation. The simulation calculation of the blanket temperature field mainly includes two parts. First, the Monte Carlo neutronics software calculates the neutron heat deposition in the blanket and its distribution. Second, the above results are used as input conditions for fluid heat transfer calculation, which can be carried out based on the computational fluid dynamics module (CFD) of ANSYS software.

[0032] The design method of the present invention plans material design, neutronics calculation, fluid heat transfer calculation, etc. according to the design objectives and requirements of the blanket, and performs iterative calculation according to the process. Among them, the conceptual design of the blanket model provides sufficient design margin for subsequent optimization design. The neutronics calculation first generates neutron heat deposition, and the fluid heat transfer calculation generates the temperature field distribution. A very important technical point and unique point in the neutronics calculation process is that the neutronics calculation includes the statistical calculation of the actual tritium production ratio in the blanket. This point focuses on solving the drawback that the conventional blanket design method can only calculate the theoretical TBR value. The present invention emphasizes the direct technical approach for tritium release effectiveness.

[0033] Under the goal of tritium self-sufficiency requirement of the fusion reactor, the present invention provides a reliable technical approach combining theory with practice for the design of advanced blanket schemes, which has important supporting significance for the future engineering implementation of the fusion reactor.

[0034] The present invention is a fusion blanket design method for controlling tritium release efficiency. The core of this design method is to obtain the actual TBR value of the blanket for judging the effectiveness of tritium self-sufficiency. Thus, it provides a more direct scientific and technological approach for obtaining an advanced blanket design scheme and for the engineering implementation of the future fusion reactor blanket.

[0035] Compared with the prior art, the present invention is designed based on the key technical nodes that have an important impact on the effectiveness of tritium release in the cladding, which is different from the conventional design method in the current fusion cladding design process that does not consider controlling the effectiveness of tritium release. Therefore, the cladding design method described in the present invention meets the tritium target requirements of the fusion reactor for the effectiveness of tritium self-sustainment. The present invention relates to a fusion cladding design method for controlling the effectiveness of tritium release. By designing the temperature field distribution of the cladding through materials and then calculating the actual TBR of the cladding, a scientific and technological approach for obtaining an optimized cladding design scheme is achieved. Among them, the MCNP software, ANSYS software, and a neutronics detection sphere method are used to assist the cladding design process. The present invention is based on adjusting the material proportion and position in each region inside the cladding to achieve the balance of the temperature field, and at the same time referring to the best temperature range requirements for effective tritium release, so as to obtain an advanced cladding design scheme, providing a scientific basis for the realization of the future fusion reactor cladding project. The entire design process described in the invention includes a necessary calculation iteration process. Based on the cladding design method described in the present invention, the physical and engineering goals of the fusion cladding can be approached and achieved. In the future, combined with the latest developments in cladding materials, neutronics, etc., a more scientific cladding design scheme can be given, but the scientific nature of the cladding design method described in the present invention remains unchanged. Based on the design method described in the present invention - from the perspective of the effectiveness of tritium release, a more practical path for cladding engineering can be obtained, so that the future fusion reactor cladding can have the function of producing tritium in a steady state and for a long time, thus effectively supporting the commercialization of future fusion reactors and providing clean energy for humanity. BRIEF DESCRIPTION OF THE DRAWINGS

[0036] Figure 1 It is a schematic diagram of the one-dimensional structure of the cladding, including the internal one-dimensional structure and the material design arrangement. It mainly prompts the description of the design method based on this structural model.

[0037] Figure 2 It is the entire implementation process of the method of the present invention, including several key technical points based on controlling the effectiveness of tritium release.

[0038] In the figure: ①, water channel; ②, breeding zone; ③, multiplier transition zone; ④, multiplier zone; ⑤, mixed breeding zone; ⑥, reduced activation steel material; ⑦, first wall surface. DETAILED DESCRIPTION OF THE EMBODIMENTS

[0039] The following examples are further explanations of the content of the present invention to illustrate the technical content of the present invention. However, the substantial content of the present invention is not limited to the following examples. Those of ordinary skill in the art can and should know that any simple change or substitution based on the substantial spirit of the present invention should fall within the protection scope required by the present invention.

[0040] Example 1

[0041] The method for designing a fusion blanket to control the effectiveness of tritium release according to the present invention includes the following steps:

[0042] 1) First, design a conceptual model of the blanket structure

[0043] According to the design objectives and requirements of the functional component tritium-producing blanket for a fusion reactor, select a solid-state water-cooled blanket structure form. As a design example, the blanket design method proposed in the present invention is described based on a blanket concept with a multi-layer structure in one-dimensional direction. The radial dimension of the blanket module is 500 mm. As Figure 1 shown in the schematic diagram of the one-dimensional blanket structure, it can be used as a case for the solid-state water-cooled blanket design used in the present invention. The structural dimensions in the other two directions of the three-dimensional space are not within the scope of the present invention. The breeder is Li4SiO4, the neutron multiplier is in the form of solid Be, the cold tube material is selected as low-activation steel material, the coolant is water medium under the cooling conditions of a pressurized water reactor, and a mixed breeder material Li4SiO4&Be 12 Ti is used in the area of the blanket far from the first wall. The breeder material and the multiplier material of the blanket can be compared and replaced according to the engineering design and physical design objectives (the selection of the blanket material is only used as a design example and is not an original invention content), but the design method proposed in the present invention is general.

[0044] 2) Blanket material design

[0045] One of the key steps in the blanket design method proposed in the present invention is the blanket material design. It is the basis for establishing the internal temperature field of the blanket and the initial stage of iterative calculation. After neutrons enter the interior of the blanket, they first react with the breeder to produce tritium, generating a large amount of neutron heat deposition in the breeding zone; in the multiplication region, they generate a multiplication effect with the multiplier to obtain more neutron doses, generating corresponding neutron heat deposition. The position and proportion of each material region will directly have a fundamental effect on the later temperature field distribution. At the same time, the width of the breeder material region in the blanket directly affects the tritium production amount, and the width of the neutron multiplication region directly affects the neutron multiplication amount. In addition, an increase or decrease in the width of each material, including the structural material and the material region of the cooling water, will have an associated impact on the tritium production amount and the temperature field distribution, that is, it is not that the larger or smaller the width of one of the materials is, the better. The material design proposed in the present invention is to find the best material design scheme for the internal material regions and proportions of the blanket.

[0046] 3) Blanket TBR calculation

[0047] The blanket TBR calculation proposed in the present invention is based on the neutronics software MCNP, that is, the Monte Carlo calculation method. According to the one-dimensional blanket structure model proposed in the present invention, parameter settings of the blanket are carried out, and the blanket parameters are input into the neutronics program for calculation to obtain the TBR value of the blanket model.

[0048] 4) Neutron thermal distribution calculation

[0049] For the cladding structure model proposed by the present invention, parametric settings of the cladding are carried out, and the cladding parameters are input into a neutronics program for calculation to obtain the neutron thermal deposition dose and its distribution in the cladding.

[0050] 5) Numerical simulation of the cladding temperature field

[0051] For the cladding structure model proposed by the present invention, a fluid heat transfer calculation model is established, grid processing is performed, and the neutron thermal deposition dose and its distribution obtained by calculation using neutronics software are used as input parameters. Based on the concept of the cladding structure proposed by the present invention, cooling boundary conditions are set. Numerical simulation calculation of the cladding temperature field is performed to obtain the temperature field distribution.

[0052] 6) Iterative calculation of the cladding temperature field and the actual TBR, including:

[0053] a. Calculate the TBR of the cladding neutronics model;

[0054] b. Simulate the cladding temperature field distribution under this model; The simulation calculation of the cladding temperature field mainly includes calculating the neutron thermal deposition and its distribution in the cladding using Monte Carlo neutronics software; and performing fluid heat transfer calculation with the aforementioned results as input conditions;

[0055] c. Refer to the optimal temperature range for effective tritium release in the cladding, and calculate the actual TBR value in combination with the neutronics detection sphere calculation method; The calculation of the actual TBR statistically calculates the tritium production distribution inside the cladding through a method of neutronics detection spheres, evaluates whether the temperature gradient range where the tritium distribution is located in each region is within the optimal temperature range required for tritium release effectiveness, and then calculates the actual tritium release ratio. On this basis, the TBR is re-evaluated to obtain the actual TBR value; The aforementioned method of neutronics detection spheres is a publicly published tritium actual calculation method. This method is used as a technical support tool for the present invention, similar to the calculation software MCNP (which can calculate neutron heat and TBR) and ANSYS (the CFD module can simulate the temperature field distribution) used in the present invention, and is not the protection point of the present invention.

[0056] d. Determine whether the cladding design scheme can meet the requirements of tritium self-sustaining effectiveness; If not, return to step (2) cladding material design, perform cladding neutronics analysis again to calculate the secondary TBR, and at the same time perform numerical analysis of the cladding temperature field and statistical calculation of the tritium breeding ratio under the condition of tritium release effectiveness again;

[0057] e. Repeat the iterative calculation steps as needed.

[0058] The cladding structure model proposed by the present invention establishes a fluid heat transfer calculation model. The temperature field distribution is obtained through step 5). Referring to the optimal temperature range for effective tritium release, the actual TBR is statistically calculated using the method of neutron detection spheres to obtain the secondary TBR value. By comparing the first TBR value, it is determined whether iterative calculation can be performed. If the tritium loss ratio can be ignored, the next step can be entered. If the tritium loss ratio can be measured, return to step 2). See the specific design flow block diagram Figure 2 , which includes controlling several key technical nodes based on the temperature field.

[0059] 7) Optimization of the cladding scheme

[0060] The first model optimization is completed according to the TBR obtained from the neutronics calculation of the cladding. Then, based on the cladding temperature distribution results and referring to the temperature range requirements under the condition of effective tritium release, the actual TBR is statistically calculated, and the cladding design scheme is optimized according to the calculation results.

[0061] It should be noted that the above technical content of the present invention is only for explaining and clarifying the technical essence of the present invention to enable those skilled in the art to understand it. Therefore, the above technical content is not used to limit the scope of the substantive protection of the present invention. The scope of the substantive protection of the present invention shall be subject to what is described in the claims. Those skilled in the art should know that any modifications, equivalent replacements, and improvements made based on the substantive spirit of the present invention shall be within the scope of the substantive protection of the present invention.

Claims

1. A design method for a fusion blanket to control the effectiveness of tritium release, comprising the following steps: 1) Selection of blanket structure model: According to the design objectives and requirements of the functional component tritium-producing blanket in a fusion reactor, select a solid-state water-cooled blanket structure model as an explanatory and illustrative case for the said design method; 2) Design of blanket materials: By adjusting the material proportion and position in each region of the blanket, achieve the design balance of the internal temperature field, and the temperature field distribution in its main breeding region meets the requirements of the optimal temperature range for effective tritium release; 3) Calculation of tritium breeding ratio TBR of the blanket: Based on the neutronics Monte Carlo calculation software MCNP, calculate the TBR value of the blanket; 4) Calculation of neutron thermal distribution: Based on the MCNP software, calculate the neutron thermal deposition of the neutronics model of the blanket to obtain the neutron thermal deposition dose and its distribution; 5) Numerical simulation of the temperature field of the blanket: Load the calculation results of the neutron thermal deposition of the blanket into the hydrodynamic model for finite element simulation calculation to obtain the temperature field distribution results; 6) Iterative calculation of the temperature field of the blanket and the actual TBR, including: a. Calculate the TBR of the neutronics model of the blanket; b. Simulate the temperature field distribution of the blanket under this model; c. Refer to the optimal temperature range for effective tritium release of the blanket, and calculate the actual TBR value in combination with the neutronics detection sphere calculation method; d. Judge whether the blanket design scheme can meet the requirements of tritium self-sustaining effectiveness; if not, return to step 2) Design of blanket materials, perform the neutronics analysis of the blanket again, calculate the secondary TBR, and at the same time perform the numerical analysis of the temperature field of the blanket again and the statistical calculation of the tritium breeding ratio under the condition of tritium release effectiveness; e. Repeat the steps of iterative calculation as needed; 7) Optimization of blanket scheme: Complete the first model optimization according to the final TBR obtained from the neutronics calculation of the blanket, then optimize the blanket scheme results according to the temperature distribution of the blanket, analyze whether the blanket meets the design requirements of effective tritium release based on the design results, and combine the aforementioned TBR calculation results to optimize the blanket design scheme.

2. The fusion blanket design method according to claim 1, wherein In the blanket material design described in step 2), the initial conditions for the design of the material region and proportion are empirical parameters. Calculate the temperature field distribution based on the preliminary results of the blanket material design, provide conditions for the subsequent judgment and evaluation of the actual TBR calculation of the blanket based on the temperature range for effective tritium release, and feedback to step 2) Design of blanket materials to adjust the blanket material design to ensure the control of the optimal temperature field distribution of the blanket.

3. The fusion blanket design method according to claim 1, characterized in that, The TBR described in step 3) is greater than 1 to meet the parameter requirements for the determination of tritium self-sustaining effectiveness.

4. The fusion blanket design method according to claim 1, characterized in that The temperature field distribution described in step 5) is related to the blanket material design and its position, and its control method is regulated through the blanket material design in step 2).

5. The fusion blanket design method according to claim 1, characterized in that, The actual TBR in step 6) is the result of continuous iterative calculation and optimization during the calculation.

6. The fusion blanket design method according to claim 1, characterized in that The simulation calculation of the temperature field of the blanket in step 6) mainly includes calculating the neutron thermal deposition and its distribution of the blanket by the Monte Carlo neutronics software; and using the aforementioned results as input conditions for fluid heat transfer calculation.

7. The fusion blanket design method according to claim 5, characterized in that Step 6) The calculation of the actual TBR is carried out by a method of neutron detection spheres to statistically calculate the tritium production distribution inside the blanket, evaluate whether the temperature gradient range where the tritium distribution in each region is located is within the optimal temperature range required for tritium release effectiveness, then calculate the actual tritium release ratio, and on this basis, re-evaluate the blanket TBR, that is, obtain the actual TBR value.

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