CN110569613A - A Method Applied to Accurate Engineering Design of Fusion Reactor Cladding - Google Patents
A Method Applied to Accurate Engineering Design of Fusion Reactor Cladding Download PDFInfo
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- 238000005253 cladding Methods 0.000 title claims abstract description 100
- 230000004927 fusion Effects 0.000 title claims abstract description 53
- 238000013461 design Methods 0.000 title claims abstract description 46
- 238000000034 method Methods 0.000 title claims abstract description 22
- 239000000463 material Substances 0.000 claims abstract description 38
- 238000004364 calculation method Methods 0.000 claims abstract description 33
- YZCKVEUIGOORGS-NJFSPNSNSA-N Tritium Chemical compound [3H] YZCKVEUIGOORGS-NJFSPNSNSA-N 0.000 claims abstract description 29
- 229910052722 tritium Inorganic materials 0.000 claims abstract description 29
- 230000004907 flux Effects 0.000 claims abstract description 15
- 238000009395 breeding Methods 0.000 claims abstract description 5
- 230000001488 breeding effect Effects 0.000 claims abstract description 5
- 238000004458 analytical method Methods 0.000 claims description 10
- 239000002245 particle Substances 0.000 claims description 5
- 239000012530 fluid Substances 0.000 claims description 4
- 238000006243 chemical reaction Methods 0.000 claims description 3
- 238000012804 iterative process Methods 0.000 claims description 3
- 230000035755 proliferation Effects 0.000 claims description 2
- 238000004088 simulation Methods 0.000 claims description 2
- 230000008878 coupling Effects 0.000 description 6
- 238000010168 coupling process Methods 0.000 description 6
- 238000005859 coupling reaction Methods 0.000 description 6
- 238000011160 research Methods 0.000 description 6
- 239000007787 solid Substances 0.000 description 6
- 230000008569 process Effects 0.000 description 4
- JWZCKIBZGMIRSW-UHFFFAOYSA-N lead lithium Chemical compound [Li].[Pb] JWZCKIBZGMIRSW-UHFFFAOYSA-N 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 239000002826 coolant Substances 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 229910052734 helium Inorganic materials 0.000 description 1
- 239000001307 helium Substances 0.000 description 1
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 1
- 230000000423 heterosexual effect Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 238000012795 verification Methods 0.000 description 1
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Abstract
一种应用于聚变堆包层精确工程设计的方法，首先进行等离子体计算获得各向异性中子源分布及包层第一壁表面热流密度分布；中子输运物理学计算中利用等离子体计算获得的各向异性中子源分布，结合热工水力学计算获得的材料温度分布，获得包层内核热热源分布及包层的氚增殖率；热工水力学计算中利用等离子体计算提供的包层第一壁表面热流密度分布及中子输运计算提供的核热热源分布获得包层内不同区域的材料温度分布；中子输运计算与热工水力学计算需进行相互迭代直至满足材料温度安全运行限制及包层氚增殖率要求；该方法能够在包层真实服役环境下针对聚变堆包层进行工程设计，克服传统方法中采用各向同性中子源与均匀包层第一壁表面热流密度的不足，实现包层的精确工程设计。
A method applied to the precise engineering design of the fusion reactor cladding. First, the plasma calculation is performed to obtain the anisotropic neutron source distribution and the heat flux distribution on the first wall surface of the cladding; the plasma calculation is used in the neutron transport physics calculation The obtained anisotropic neutron source distribution, combined with the material temperature distribution obtained by thermal hydraulics calculation, obtains the thermal heat source distribution in the inner core of the cladding and the tritium breeding rate of the cladding; in the thermal hydraulics calculation, the package provided by the plasma calculation is used. The heat flux distribution on the surface of the first wall of the layer and the nuclear heat source distribution provided by the neutron transport calculation can obtain the material temperature distribution in different regions in the cladding; the neutron transport calculation and thermal hydraulic calculation need to iterate each other until the material temperature is satisfied. Safe operation limits and cladding tritium multiplication rate requirements; this method can carry out engineering design for the fusion reactor cladding under the real service environment of the cladding, overcoming the isotropic neutron source and uniform heat flow on the surface of the first wall of the cladding in the traditional method The lack of density enables precise engineering of the cladding.
Description
技术领域technical field
本发明涉及聚变堆包层设计技术领域，具体涉及一种聚变堆包层精确工程设计的方法，是一种获得真实服役环境下聚变堆包层工程设计参数的方法。The invention relates to the technical field of cladding design of a fusion reactor, in particular to a method for precise engineering design of a cladding of a fusion reactor, and is a method for obtaining engineering design parameters of a cladding of a fusion reactor in a real service environment.
背景技术Background technique
包层在聚变堆中承担能量转换、氚增殖及辐射屏蔽等重要功能，其中，冷却剂在大量并联管中流动带走包层内的热量，中子倍增剂用于增加中子通量以提高氚增殖剂的氚增殖比，而聚变堆堆芯中的燃料处于高温(上亿度)等离子体状态，会对包层的运行工况产生重要影响。等离子体运行期间会产生大量的中子和热量脉冲，通过径向输运流向包层第一壁，给包层结构设计在工程上带来巨大的挑战，因此包层结构的设计需要结合等离子体物理学、中子输运物理学、热工流体力学等多个物理场确定包层的结构参数。The cladding is responsible for important functions such as energy conversion, tritium breeding, and radiation shielding in the fusion reactor. Among them, the coolant flows in a large number of parallel tubes to take away the heat in the cladding, and the neutron multiplier is used to increase the neutron flux to improve The tritium breeding ratio of the tritium breeder, and the fuel in the fusion reactor core is in a high-temperature (hundred million degrees) plasma state, which will have an important impact on the operating conditions of the cladding. During the operation of the plasma, a large number of neutrons and heat pulses will be generated, which flow to the first wall of the cladding through radial transport, which brings great engineering challenges to the design of the cladding structure. Therefore, the design of the cladding structure needs to combine plasma Physics, neutron transport physics, thermal fluid mechanics and other physical fields determine the structural parameters of the cladding.
目前针对ITER和CFETR包层在正常和极端工况下的设计研究中，均假设包层第一壁表面热流密度均匀且为定值，不符合包层在托卡马克装置中的真实服役环境，采用的热流密度值也均趋于保守，不仅增加了包层的设计难度，而且不能满足聚变堆包层的详细工程设计需求。如Songlin Liu等在一篇公开期刊文献(Songlin Liu,Yong Pu,XiaomanCheng,et al.,Conceptual design of a water cooled breeder blanket for CFETR,Fusion Engineering and Design 89(2014)1380–1385.)中针对CFETR水冷固态增殖包层的设计研究中采用的第一壁表面热流密度为均匀的0.3MW/m2，Hongli Chen等在一篇公开期刊文献(Chen HL,Li M,Lv ZL,et al.Conceptual design and analysis of thehelium cooled solid breeder blanket for CFETR,Fusion Engineering and Design96–97(2015)89–94)中针对CFETR氦冷固态增殖包层的设计研究中采用的第一壁表面热流密度也为均匀的0.3MW/m2，国外J.Aubert等在一篇公开期刊文献(J.Aubert,G.Aiello,N.Jonquères,et al.,Development of the water cooled lithium lead blanket forDEMO,Fusion Engineering and Design 89(2014)1386–1391)中针对欧洲聚变示范堆水冷锂铅包层的分析研究中采用的第一壁表面热流密度为均匀的0.5MW/m2。同时，上述文献中均采用了各向同性均匀中子源假设，赵奉超等在一篇公开文献(赵奉超，冯开明，曹启祥，等，核聚变与等离子体物理38(2018)48–54)中针对CFETR进行的中子学分析中也采用了各向同性的体积中子源。At present, in the design research of ITER and CFETR cladding under normal and extreme working conditions, it is assumed that the heat flux on the surface of the first wall of the cladding is uniform and constant, which does not meet the real service environment of the cladding in the tokamak device. The heat flux values adopted also tend to be conservative, which not only increases the difficulty of cladding design, but also cannot meet the detailed engineering design requirements of fusion reactor cladding. For example, Songlin Liu et al. (Songlin Liu, Yong Pu, XiaomanCheng, et al., Conceptual design of a water cooled breeder blanket for CFETR, Fusion Engineering and Design 89(2014) 1380–1385.) in a public journal document for CFETR The heat flux on the surface of the first wall used in the design study of the water-cooled solid-state propagation cladding is uniform 0.3MW/m 2 , Hongli Chen et al. published an open journal document (Chen HL, Li M, Lv ZL, et al. and analysis of thehelium cooled solid breeder blanket for CFETR, Fusion Engineering and Design96–97(2015)89–94), the first wall surface heat flux used in the design research for CFETR helium cooled solid breeder blanket is also uniform 0.3 MW/m 2 , foreign J.Aubert etc. in an open journal literature (J.Aubert, G.Aiello, N.Jonquères, et al., Development of the water cooled lithium lead blanket for DEMO, Fusion Engineering and Design 89 (2014 ) 1386–1391) in the analysis of the water-cooled lithium-lead cladding of the European Fusion Demonstration Reactor adopted a uniform heat flux of 0.5MW/m 2 on the surface of the first wall. At the same time, the assumption of an isotropic uniform neutron source is adopted in the above-mentioned literatures. In a public literature (Zhao Fengchao, Feng Kaiming, Cao Qixiang, et al., Nuclear Fusion and Plasma Physics 38 (2018) 48–54), Zhao Fengchao et al. An isotropic bulk neutron source was also used in the neutronics analysis performed at CFETR.
这些研究中均没有考虑聚变堆堆芯高温等离子体对包层的影响，只是采用了简单的均匀热流密度和各向同性中子源假设进行包层的设计及分析，只能适用于包层的概念设计阶段，难以实现聚变堆包层真实服役环境的模拟，无法研究聚变堆芯高温等离子体的粒子及热量脉冲对包层运行的影响，更不能满足聚变堆包层的详细工程设计需求。These studies did not consider the influence of the high-temperature plasma of the fusion reactor core on the cladding, but only adopted the simple assumption of uniform heat flux and isotropic neutron source for the design and analysis of the cladding, which can only be applied to the cladding. In the conceptual design stage, it is difficult to simulate the real service environment of the fusion reactor cladding, and it is impossible to study the influence of particles and heat pulses of the high-temperature plasma of the fusion reactor core on the cladding operation, let alone meet the detailed engineering design requirements of the fusion reactor cladding.
发明内容Contents of the invention
为了克服上述现有方法存在的问题，本发明的目的是为了提出一种基于多物理场耦合的应用于聚变堆包层精确工程设计的方法，从而弥补现有分析设计方法未能模拟包层真实服役环境的不足。In order to overcome the problems existing in the above-mentioned existing methods, the purpose of the present invention is to propose a method based on multi-physics field coupling applied to the precise engineering design of the fusion reactor cladding, so as to make up for the failure of the existing analysis and design methods to simulate the real cladding. Insufficient service environment.
本发明采取以下技术方案达到上述目的：The present invention takes the following technical solutions to achieve the above object:
一种应用于聚变堆包层精确工程设计的方法，包括如下步骤：A method applied to the precise engineering design of fusion reactor cladding, comprising the following steps:
步骤1：根据聚变堆堆芯等离子体运行参数，采用等离子体输运程序构建聚变堆堆芯等离子体模型，通过等离子体粒子及能量径向输运模拟计算，获得聚变堆堆芯内的各向异性中子源分布及包层第一壁表面热流密度分布；Step 1: According to the plasma operating parameters of the fusion reactor core, the plasma model of the fusion reactor core is constructed by using the plasma transport program, and the radial transport of plasma particles and energy is simulated and calculated to obtain all directions in the fusion reactor core. The distribution of heterosexual neutron sources and the heat flux distribution on the surface of the first wall of the cladding;
步骤2：根据聚变堆包层初始的结构材料、中子倍增剂、氚增殖剂的布置及尺寸参数，采用中子输运程序构建聚变堆包层的中子输运分析模型，以步骤1获得的各向异性中子源分布为基础，结合假定的材料温度分布，获得聚变堆包层内的核热热源分布以及包层的氚增殖率；Step 2: According to the initial structural materials of the fusion reactor cladding, the arrangement and size parameters of neutron multipliers and tritium multipliers, use the neutron transport program to construct the neutron transport analysis model of the fusion reactor cladding, and obtain in step 1 Based on the distribution of anisotropic neutron sources, combined with the assumed material temperature distribution, the distribution of nuclear heat sources in the envelope of the fusion reactor and the tritium multiplication rate of the envelope are obtained;
步骤3：根据聚变堆包层的几何结构及材料组分，采用计算流体动力学程序构建聚变堆包层的热工水力分析模型，以步骤1获得的包层第一壁表面热流密度分布为基础，结合步骤2获得的聚变堆包层内核热热源分布，获得聚变堆包层内不同区域的材料温度；Step 3: According to the geometric structure and material composition of the fusion reactor cladding, the computational fluid dynamics program is used to construct the thermal hydraulic analysis model of the fusion reactor cladding, based on the heat flux distribution on the first wall surface of the cladding obtained in step 1 , combined with the heat source distribution of the fusion reactor cladding core obtained in step 2, the material temperatures in different regions of the fusion reactor cladding are obtained;
步骤4：由于不同温度下聚变堆包层内中子与材料的反应截面不同，导致其释放的热量即包层内核热热源不同，因此中子输运计算与热工水力计算需要进行双向耦合迭代，中子输运计算为热工水力计算提供核热热源分布，热工水力计算为中子输运计算提供不同材料温度分布，二者相互迭代，即交替重复步骤2及步骤3，但步骤2初次进行过程中采用的“假定的材料温度分布”在迭代过程中需调整为步骤3获得的聚变堆包层内材料温度分布，迭代计算直至该包层结构设计参数下的氚增殖率及温度分布均收敛。Step 4: Due to the different reaction cross-sections of neutrons and materials in the cladding of the fusion reactor at different temperatures, the heat released by them, that is, the heat source of the cladding core, is different. Therefore, neutron transport calculations and thermal hydraulic calculations need to be bidirectionally coupled and iterative , the neutron transport calculation provides the nuclear heat source distribution for the thermal-hydraulic calculation, and the thermal-hydraulic calculation provides the temperature distribution of different materials for the neutron transport calculation. The "assumed material temperature distribution" used in the initial process needs to be adjusted to the material temperature distribution in the fusion reactor cladding obtained in step 3 during the iterative process, and iteratively calculated until the tritium proliferation rate and temperature distribution under the cladding structure design parameters Both converge.
步骤5：检验步骤4获得的聚变堆包层的氚增殖率及温度分布是否满足材料温度限制及氚增殖率要求，若同时满足材料温度限制及氚增殖率要求，则输出该包层结构设计参数；若不能同时满足材料温度限制及氚增殖率要求，则修改包层的结构设计参数后执行步骤2到步骤5，直至满足材料温度限制及包层氚增殖率要求。Step 5: Check whether the tritium multiplication rate and temperature distribution of the cladding of the fusion reactor obtained in step 4 meet the material temperature limit and tritium multiplication rate requirements, and if both meet the material temperature limit and tritium multiplication rate requirements, then output the cladding structure design parameters ; If the material temperature limit and tritium multiplication rate requirements cannot be met at the same time, then modify the structural design parameters of the cladding and then perform steps 2 to 5 until the material temperature limit and cladding tritium multiplication rate requirements are met.
和现有技术相比较，本发明具备如下优点及创新点：Compared with the prior art, the present invention has the following advantages and innovations:
1、该设计方法基于多学科交叉，综合等离子体基础研究及包层实际工程应用需求，得到包层多物理场耦合设计技术；1. The design method is based on interdisciplinary, comprehensive plasma basic research and cladding practical engineering application requirements, and obtains cladding multi-physics field coupling design technology;
2、该设计方法突破现有包层设计研究中缺乏堆芯等离子体影响的局限，获得多场耦合条件下包层热工安全特性；2. This design method breaks through the limitations of the lack of core plasma influence in the existing cladding design research, and obtains the thermal safety characteristics of the cladding under the condition of multi-field coupling;
3、该设计方法采用采用多物理场耦合进行聚变堆包层的设计研究，为包层的实际运行状态提供精确借鉴。3. This design method uses multi-physics field coupling to carry out the design research of the fusion reactor cladding, which provides accurate reference for the actual operating state of the cladding.
总而言之，本发明设计方法基于等离子体、热工水力、粒子输运等多物理场耦合提供聚变堆包层精确工程设计方法，所得结果更符合包层的实际运行工况，同时可为聚变堆包层的堆内实验校核提供指导。All in all, the design method of the present invention provides an accurate engineering design method for the fusion reactor cladding based on the coupling of multiple physical fields such as plasma, thermal hydraulics, and particle transport. In-core experimental verification of layers provides guidance.
附图说明Description of drawings
图1聚变堆包层精确工程设计方法流程图。Fig. 1 Flowchart of accurate engineering design method for fusion reactor cladding.
图2聚变堆包层布置及等离子体分布示意图。Fig. 2 Schematic diagram of cladding layout and plasma distribution of fusion reactor.
具体实施方式Detailed ways
以下结合附图及具体实施例对本发明作进一步的详细说明。The present invention will be further described in detail below in conjunction with the accompanying drawings and specific embodiments.
根据本发明的一个实施例，采用如图1所示的流程开展CFETR一期氦冷固态包层的设计研究，CFETR包层布置及等离子分布如图2所示。According to an embodiment of the present invention, the design and research of the first-stage helium-cooled solid-state cladding of CFETR is carried out using the process shown in FIG. 1 , and the cladding layout and plasma distribution of CFETR are shown in FIG. 2 .
1.根据CFETR一期的堆芯运行设计参数利用等离子体输运程序如BOUT++等建立CFETR堆芯等离子体模型，主要参数包括大半径6.62m、小半径1.79m、中心电流密度4.6MA/m2、中心纵场场强5.77T、聚变堆功率200.4MW等，通过CFETR堆芯等离子体粒子及能量径向输运模拟计算，获得CFETR堆芯内的各向异性中子源分布及氦冷固态包层第一壁表面热流密度分布；1. Establish a CFETR core plasma model based on the core operation design parameters of the first phase of CFETR using plasma transport programs such as BOUT++. The main parameters include a large radius of 6.62m, a small radius of 1.79m, and a central current density of 4.6MA/m 2 , central longitudinal field strength 5.77T, fusion reactor power 200.4MW, etc., through the CFETR core plasma particle and energy radial transport simulation calculation, the anisotropic neutron source distribution and helium-cooled solid-state package in the CFETR core are obtained Heat flux distribution on the surface of the first wall of the layer;
2.根据CFETR氦冷固态包层概念设计的结构材料、中子倍增剂、氚增殖剂的布置方案及尺寸参数，利用中子输运程序如MCNP等搭建CFETR氦冷固态包层的中子输运分析模型，以步骤1获得的各向异性中子源分布为基础，结合假定的材料温度分布，获得CFETR氦冷固态包层内的核热热源分布以及包层的氚增殖率；2. According to the structural material, neutron multiplier, and tritium multiplier layout scheme and size parameters designed according to the concept of CFETR helium-cooled solid-state cladding, use neutron transport programs such as MCNP to build the neutron transport of CFETR helium-cooled solid-state cladding Using the analytical model, based on the anisotropic neutron source distribution obtained in step 1, combined with the assumed material temperature distribution, the nuclear heat source distribution in the CFETR helium-cooled solid-state cladding and the tritium multiplication rate of the cladding are obtained;
3.根据CFETR氦冷固态包层概念设计的几何结构及材料组分，采用计算流体动力学程序如Fluent等构建CFETR氦冷固态包层热工水力分析模型，以步骤1获得的CFETR氦冷固态包层第一壁表面热流密度分布为基础，结合步骤2获得的CFETR氦冷固态包层内核热热源分布，获得CFETR氦冷固态包层内不同区域的材料温度；3. According to the geometric structure and material composition of the conceptual design of the CFETR helium-cooled solid-state cladding, a computational fluid dynamics program such as Fluent is used to construct the thermal-hydraulic analysis model of the CFETR helium-cooled solid-state cladding, and the CFETR helium-cooled solid-state cladding obtained in step 1 Based on the heat flux distribution on the surface of the first wall of the cladding, combined with the heat source distribution in the inner core of the CFETR helium-cooled solid cladding obtained in step 2, the material temperature in different regions in the CFETR helium-cooled solid cladding is obtained;
4.中子输运计算与热工水力计算的双向耦合迭代，MCNP中子输运计算为FLUENT热工水力计算提供核热热源，FLUENT热工水力计算为MCNP中子输运计算提供不同材料温度，二者相互迭代，交替重复步骤2及步骤3，但步骤2初次进行过程中采用的“假定的材料温度分布”在迭代过程中需调整为步骤3获得的CFETR氦冷固态包层内材料温度分布，迭代计算直至该包层结构设计参数下CFETR氦冷固态包层内的氚增殖率及温度分布均收敛。4. Two-way coupling iteration of neutron transport calculation and thermal-hydraulic calculation, MCNP neutron transport calculation provides nuclear heat source for FLUENT thermal-hydraulic calculation, FLUENT thermal-hydraulic calculation provides different material temperatures for MCNP neutron transport calculation , the two iterate each other, and repeat step 2 and step 3 alternately, but the "assumed material temperature distribution" used in the initial process of step 2 needs to be adjusted to the material temperature in the CFETR helium-cooled solid-state cladding obtained in step 3 during the iterative process Distribution, iterative calculation until the tritium multiplication rate and temperature distribution in the CFETR helium-cooled solid-state cladding converge under the cladding structure design parameters.
5.检验步骤4获得的CFETR氦冷固态包层的氚增殖率及温度分布是否满足材料温度限制及氚增殖率要求，若同时满足材料温度限制及氚增殖率要求，则输出该CFETR氦冷固态包层的结构设计参数；若不能同时满足材料温度限制及氚增殖率要求，则修改CFETR氦冷固态包层的结构设计参数后执行步骤2到步骤5，直至CFETR氦冷固态包层结构设计参数满足材料温度限制及包层氚增殖率要求。5. Check whether the tritium multiplication rate and temperature distribution of the CFETR helium-cooled solid cladding obtained in step 4 meet the material temperature limit and tritium multiplication rate requirements. If both meet the material temperature limit and tritium multiplication rate requirements, then output the CFETR helium-cooled solid state The structural design parameters of the cladding; if the material temperature limit and the tritium multiplication rate requirements cannot be met at the same time, then modify the structural design parameters of the CFETR helium-cooled solid-state cladding and perform steps 2 to 5 until the structural design parameters of the CFETR helium-cooled solid-state cladding Satisfy material temperature limit and cladding tritium multiplication rate requirements.
以上所述的，仅为本发明的实施例，并非用以限定本发明的范围，本发明的上述实施例还可以做出各种变化。即凡是依据本发明申请的权利要求书及说明书内容所做的简单、等效变化与修饰，皆落入本发明专利的权利要求保护范围。本发明未详尽描述的均为常规技术内容。What is described above is only an embodiment of the present invention, and is not intended to limit the scope of the present invention. Various changes can also be made to the above-mentioned embodiments of the present invention. That is to say, all simple and equivalent changes and modifications made according to the claims of the present application and the contents of the description fall within the protection scope of the claims of the present invention patent. What is not described in detail in the present invention is conventional technical content.
基于以上的理论模型，该发明的计算流程如图1所示，聚变堆内包层布置及等离子体分布如图2所示。Based on the above theoretical model, the calculation process of the invention is shown in Figure 1, and the cladding layout and plasma distribution in the fusion reactor are shown in Figure 2.
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