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CN116522682A - A Calculation Method of Heat Flux in the First Wall of Tokamak Fusion Reactor - Google Patents

A Calculation Method of Heat Flux in the First Wall of Tokamak Fusion Reactor Download PDF

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CN116522682A
CN116522682A CN202310698237.0A CN202310698237A CN116522682A CN 116522682 A CN116522682 A CN 116522682A CN 202310698237 A CN202310698237 A CN 202310698237A CN 116522682 A CN116522682 A CN 116522682A
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田文喜
李昕泽
张大林
苏光辉
秋穗正
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Abstract

The invention discloses a calculation method of heat flux density of a first wall of a Tokamak fusion reactor, which is used for establishing a radiation heat exchange three-dimensional calculation model and a charged particle heat flux density three-dimensional calculation model based on plasma configuration, a magnetic field and spatial distribution of the first wall; the method comprises the steps of carrying out iteration on plasma temperature by referring to a conservative average heat flux density designed by Tokamak of a radiation heat exchange three-dimensional calculation model, and obtaining first wall radiation heat flux density distribution when the average heat flux densities are consistent; the three-dimensional calculation model of the heat flux density of the charged particles establishes the space projection of the charged particles on the first wall according to the plasma configuration and the magnetic field space distribution, and obtains the heat flux density distribution of the charged particles on the first wall by combining the attenuation outside the outermost closed magnetic surface; according to the method, the influence of radiation heat exchange between the first walls, the space coordinates and the magnetic field distribution on the heat flux density is considered, the fine calculation result of the heat flux density of the first walls is obtained, the input errors of the heat exchange of the first walls and the structural calculation are reduced, and the design cost is reduced.

Description

一种托卡马克聚变堆第一壁热流密度计算方法A Calculation Method of Heat Flux in the First Wall of Tokamak Fusion Reactor

技术领域technical field

本发明专利涉及托卡马克聚变堆技术领域,具体涉及一种托卡马克聚变堆第一壁热流密度计算方法。The patent of the present invention relates to the technical field of tokamak fusion reactor, in particular to a method for calculating the heat flux density of the first wall of the tokamak fusion reactor.

背景技术Background technique

托卡马克是一种通过电磁场约束、驱动,创造氘、氚实现聚变的环境和超高温,并实现可控核聚变反应的装置。第一壁是托卡马克聚变反应过程中直接面对等离子体的固体结构。它用于封闭真空室,并吸收等离子体释放的辐射能和部分带电粒子能。Tokamak is a device that creates an environment and ultra-high temperature for fusion of deuterium and tritium through electromagnetic field confinement and drive, and realizes controllable nuclear fusion reactions. The first wall is the solid structure that directly faces the plasma during the tokamak fusion reaction. It is used to seal the vacuum chamber and absorb the radiation energy and part of the charged particle energy released by the plasma.

在此背景下,近些年展开了大量的托卡马克聚变堆设计,第一壁作为真空室和包层的重要部件,其表面承受的热流密度是设计过程中的重要边界条件,是第一壁最主要的安全性载荷。但针对第一壁的热流密度计算没有统一的方法,其中辐射热流密度多采用堆芯功率进行估算,并使用均匀载荷加载在第一壁,这种方法忽略了辐射热流密度的空间不均匀性,无法对载荷集中的区域进行重点分析;带电粒子热流密度在计算过程中多采用球形简化,并且由于其结果对三维空间相对位置极其敏感,现有方法缺少对带电粒子在第一壁的准确结果;同时,现有方法缺少对两种第一壁热流密度的耦合计算方法,无法提供完整的热流密度计算结果,计算效率较低,缺乏经济型。In this context, a large number of tokamak fusion reactor designs have been carried out in recent years. The first wall is an important part of the vacuum chamber and the cladding, and the heat flux on its surface is an important boundary condition in the design process. It is the first The most important safety load of the wall. However, there is no unified method for calculating the heat flux of the first wall. The radiation heat flux is mostly estimated by the core power and loaded on the first wall with a uniform load. This method ignores the spatial inhomogeneity of the radiation heat flux. It is impossible to focus on the area where the load is concentrated; the heat flux of charged particles is mostly simplified by spherical simplification in the calculation process, and because the result is extremely sensitive to the relative position in three-dimensional space, the existing methods lack accurate results for charged particles on the first wall; At the same time, the existing method lacks a coupling calculation method for the heat flux density of the two first walls, and cannot provide complete heat flux calculation results, and the calculation efficiency is low, and it is not economical.

发明内容Contents of the invention

为解决上述问题,实现第一壁辐射热流密度和带电粒子热流密度的三维空间精确计算,本发明的目的在于提供一种托卡马克聚变堆第一壁热流密度计算方法,本发明提供了完整有效的托卡马克聚变堆第一壁热流密度计算方法,考虑了第一壁三维空间下与等离子体的相对角度和距离对热流密度的影响,考虑了磁场分布对热流密度的影响,考虑了第一壁间的辐射换热,对第一壁热流密度的空间分布具有更高的精度,降低了第一壁换热与结构计算的输入性误差,降低了设计成本。In order to solve the above problems and realize the three-dimensional accurate calculation of the first wall radiation heat flux and charged particle heat flux, the object of the present invention is to provide a method for calculating the first wall heat flux of a Tokamak fusion reactor. The present invention provides a complete and effective The calculation method of the heat flux of the first wall of the tokamak fusion reactor considers the influence of the relative angle and distance of the first wall to the plasma in the three-dimensional space on the heat flux, the influence of the magnetic field distribution on the heat flux, and the first The radiation heat exchange between the walls has higher accuracy for the spatial distribution of the heat flux density of the first wall, which reduces the input error of the first wall heat transfer and structural calculation, and reduces the design cost.

为了达到上述目的,本发明采用的技术方案如下:In order to achieve the above object, the technical scheme adopted in the present invention is as follows:

一种托卡马克聚变堆第一壁热流密度计算方法,该方法基于等离子体位形、磁场空间分布和第一壁空间分布,根据第一壁热流密度来源,分别建立辐射换热三维计算模型和带电粒子热流密度三维计算模型;A method for calculating the heat flux density of the first wall of a tokamak fusion reactor. The method is based on the plasma configuration, the spatial distribution of the magnetic field, and the spatial distribution of the first wall. 3D calculation model of particle heat flux;

辐射换热三维计算模型参考托卡马克聚变堆工程设计的保守平均热流密度,对等离子体温度进行迭代计算,最终得到平均热流密度一致时的第一壁辐射热流密度分布;The three-dimensional calculation model of radiation heat transfer refers to the conservative average heat flux of the Tokamak fusion reactor engineering design, iteratively calculates the plasma temperature, and finally obtains the radiation heat flux distribution of the first wall when the average heat flux is consistent;

带电粒子热流密度三维计算模型根据等离子体位形和磁场空间分布建立带电粒子在第一壁上的空间投影,并考虑带电粒子在最外闭合磁面外的衰减,最终得到第一壁上带电粒子热流密度分布;The three-dimensional calculation model of the charged particle heat flux density establishes the spatial projection of the charged particles on the first wall according to the plasma configuration and the spatial distribution of the magnetic field, and considers the attenuation of the charged particles outside the outermost closed magnetic surface, and finally obtains the charged particle heat flux on the first wall density distribution;

该方法计算对象包括第一壁1、等离子体2;其中第一壁1根据托卡马克聚变堆设计进行排布,等离子体2为计算工况下位形的最外闭合磁面;The calculation object of this method includes the first wall 1 and the plasma 2; wherein the first wall 1 is arranged according to the design of the tokamak fusion reactor, and the plasma 2 is the outermost closed magnetic surface of the configuration under the calculation condition;

进行计算时,需已知或能够初步获得以下参数:第一壁材料许用温度T0、第一壁材料辐射度ε、计算工况下的等离子体位形最外闭合磁面空间坐标、第一壁设计结构及空间坐标、聚变堆第一壁的设计保守平均热流密度Q0、磁场空间分布B、工况下衰减长度λq和最后闭合磁力线平行热流密度q0When calculating, the following parameters need to be known or can be preliminarily obtained: the allowable temperature T 0 of the first wall material, the radiation degree ε of the first wall material, the space coordinates of the outermost closed magnetic surface of the plasma configuration under the calculation conditions, the first Wall design structure and space coordinates, design conservative average heat flux Q 0 of the first wall of the fusion reactor, magnetic field spatial distribution B, decay length λ q under working conditions, and final closed magnetic flux parallel heat flux q 0 .

具体的,本发明方法包括以下步骤:Specifically, the inventive method comprises the following steps:

步骤1,建立辐射换热三维计算模型:根据托卡马克设计中等离子体位形最外闭合磁面空间坐标和第一壁空间坐标建立辐射换热三维计算模型的完整三维结构,根据完整三维结构环向对称性,选取最小重复结构作为计算使用的三维结构;Step 1, establish the 3D calculation model of radiation heat transfer: according to the space coordinates of the outermost closed magnetic surface of the plasma configuration and the space coordinates of the first wall in the tokamak design, establish the complete 3D structure of the 3D calculation model of radiation heat transfer, and according to the complete 3D structure loop Symmetry, select the minimum repeating structure as the three-dimensional structure used in the calculation;

辐射换热计算基于有限元法进行离散,辐射换热计算公式采用斯蒂芬-玻耳兹曼定律,辐射发射功率E表达式为:The radiation heat transfer calculation is discrete based on the finite element method, and the radiation heat transfer calculation formula adopts the Stephen-Boltzmann law, and the radiation emission power E expression is:

E=σT4 E=σT 4

其中σ为玻尔兹曼常数;where σ is the Boltzmann constant;

根据热平衡,第一壁辐射热流密度分布qr为对应点总入射辐射热流密度G减去总漫反射热流密度J=ρdG+E(T0)和总镜面反射热流密度ρsG,其中ρd为漫反射系数,ρs为镜面反射系数,并有ε=1-(ρds),最终表达式为:According to heat balance, the radiation heat flux distribution q r of the first wall is the total incident radiation heat flux G minus the total diffuse reflection heat flux J=ρ d G+E(T 0 ) and the total specular reflection heat flux ρ s G at the corresponding point, where ρ d is the diffuse reflection coefficient, ρ s is the specular reflection coefficient, and ε=1-(ρ ds ), the final expression is:

qr=G-(J+ρsG)=ε(E(T)-E(T0))q r =G-(J+ρ s G)=ε(E(T)-E(T 0 ))

式中:E(T)为等离子体辐射发射功率,E(T0)为第一壁辐射发射功率;表达式中选取第一壁材料许用温度T0作为第一壁温度,空间距离与表面法向夹角由三维结构坐标得到,等离子体温度T为未知量,使用迭代法对等离子体温度T进行迭代计算,直到三维结构所有坐标计算得到的qr的平均值与Q0相等,选取此时的第一壁辐射热流密度分布qr作为模型计算结果;In the formula: E(T) is the radiation emission power of the plasma, E(T 0 ) is the radiation emission power of the first wall; in the expression, the allowable temperature T 0 of the first wall material is selected as the temperature of the first wall, and the spatial distance and the surface The normal angle is obtained from the coordinates of the three-dimensional structure, and the plasma temperature T is an unknown quantity. The iterative method is used to iteratively calculate the plasma temperature T until the average value of q r calculated by all coordinates of the three-dimensional structure is equal to Q 0 . The radiation heat flux distribution q r of the first wall at time is taken as the model calculation result;

步骤2,建立带电粒子热流密度三维计算模型:带电粒子热流密度三维计算模型采用与步骤1相同三维结构;带电粒子热流密度计算采用有限元法进行离散,首先已知磁场空间分布B,选取三维结构中每个计算点磁场方向作为其坐标处带电粒子方向,如果磁场为托卡马克坐标,则对磁场托卡马克坐标进行笛卡尔坐标代换,表达式为:Step 2, establish a three-dimensional calculation model of charged particle heat flux: the three-dimensional calculation model of charged particle heat flux adopts the same three-dimensional structure as step 1; the calculation of charged particle heat flux adopts the finite element method for discretization, firstly, the spatial distribution B of the magnetic field is known, and the three-dimensional structure is selected The direction of the magnetic field at each calculation point in is taken as the direction of the charged particles at its coordinates. If the magnetic field is a tokamak coordinate, the Cartesian coordinates are substituted for the magnetic field tokamak coordinates, and the expression is:

由于磁场具备环向均匀性,B(r,phi,z)=B(r,z),B(r,phi,z)为随托卡马克坐标变化的磁场,B(r,z)为随托卡马克坐标变化的轴对称磁场;磁场平行热流密度q采用指数衰减模型,表达式为:Since the magnetic field has circumferential uniformity, B(r, phi, z) = B(r, z), B(r, phi, z) is the magnetic field that changes with the coordinates of the tokamak, and B(r, z) is the The axisymmetric magnetic field of the tokamak coordinate change; the parallel heat flux q of the magnetic field adopts the exponential decay model, and the expression is:

其中q为磁场平行热流密度,q0为最后闭合磁力线平行热流密度,d为计算点与最外闭合磁面空间距离,λq为工况下衰减长度;Where q is the heat flux parallel to the magnetic field, q 0 is the heat flux parallel to the last closed magnetic force line, d is the spatial distance between the calculation point and the outermost closed magnetic surface, and λ q is the attenuation length under working conditions;

则第一壁上带电粒子热流密度qb为:Then the heat flux q b of charged particles on the first wall is:

其中n为计算点法向量,nx、ny、nz分别为计算点法向量在笛卡尔坐标系下分量,Bphi、Br、Bz分别为磁场空间分布B在托卡马克坐标系下分量,此时qb为模型计算结果。Where n is the normal vector of the calculation point, n x , ny , and nz are the components of the normal vector of the calculation point in the Cartesian coordinate system, B phi , B r , and B z are the magnetic field spatial distribution B in the tokamak coordinate system The lower component, at this time q b is the model calculation result.

和现有技术相比较,本发明具备如下优点:Compared with the prior art, the present invention has the following advantages:

1、本发明提供了完整有效的托卡马克聚变堆第一壁热流密度计算方法,考虑了第一壁三维空间下与等离子体的相对角度和距离对热流密度的影响,考虑了磁场分布对热流密度的影响,考虑了第一壁间的辐射换热,对第一壁热流密度的空间分布的计算具有更高的精度,降低了第一壁换热与结构计算的输入性误差。1. The present invention provides a complete and effective calculation method for the heat flux of the first wall of the Tokamak fusion reactor, which considers the influence of the relative angle and distance from the first wall to the plasma in the three-dimensional space on the heat flux, and considers the influence of the magnetic field distribution on the heat flux The influence of density takes into account the radiation heat transfer between the first walls, and the calculation of the spatial distribution of the heat flux density of the first wall has higher accuracy, which reduces the input error of the first wall heat transfer and structure calculation.

2、本发明提供辐射热流密度和带电粒子热流密度的统一计算方法,降低了设计成本。2. The present invention provides a unified calculation method for radiation heat flux density and charged particle heat flux density, which reduces the design cost.

3、本发明设计流程短、效率高、计算模块化可操作性强,很大程度缩短了分析与设计的时间。3. The present invention has short design process, high efficiency, and strong operability of calculation modularization, which greatly shortens the time of analysis and design.

附图说明Description of drawings

图1为一种托卡马克聚变堆第一壁热流密度计算方法示意图。Fig. 1 is a schematic diagram of a method for calculating the heat flux density of the first wall of a tokamak fusion reactor.

图2为第一壁与等离子体模型。Figure 2 is the first wall and plasma model.

图3为辐射热流密度计算结果。Figure 3 shows the calculation results of radiation heat flux.

图4为带电粒子热流密度计算结果。Figure 4 shows the calculation results of the charged particle heat flux.

具体实施方式Detailed ways

为使本发明实施例的目的、技术方案和优点更加清楚,下面将结合本发明实施例中的附图,对本发明实施例中的技术方案进行清楚、完整地描述,显然,所描述的实施例是本发明一部分实施例,而不是全部的实施例。基于本发明中的实施例,本领域普通技术人员在没有作出创造性劳动前提下所获得的所有其他实施例,都属于本发明保护的范围。In order to make the purpose, technical solutions and advantages of the embodiments of the present invention clearer, the technical solutions in the embodiments of the present invention will be clearly and completely described below in conjunction with the drawings in the embodiments of the present invention. Obviously, the described embodiments It is a part of embodiments of the present invention, but not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by persons of ordinary skill in the art without creative efforts fall within the protection scope of the present invention.

本发明一种托卡马克聚变堆第一壁热流密度计算方法,该方法基于等离子体位形、磁场空间分布和第一壁空间分布,根据第一壁热流密度来源,分别建立辐射换热三维计算模型和带电粒子热流密度三维计算模型;The invention discloses a method for calculating the heat flux density of the first wall of a tokamak fusion reactor. The method is based on the plasma configuration, the spatial distribution of the magnetic field and the spatial distribution of the first wall, and respectively establishes a three-dimensional calculation model of radiation heat transfer according to the source of the heat flux density of the first wall. and a three-dimensional calculation model of charged particle heat flux;

辐射换热三维计算模型参考托卡马克聚变堆工程设计的保守平均热流密度,对等离子体温度进行迭代计算,最终得到平均热流密度一致时的第一壁辐射热流密度分布;The three-dimensional calculation model of radiation heat transfer refers to the conservative average heat flux of the Tokamak fusion reactor engineering design, iteratively calculates the plasma temperature, and finally obtains the radiation heat flux distribution of the first wall when the average heat flux is consistent;

带电粒子热流密度三维计算模型根据等离子体位形和磁场空间分布建立带电粒子在第一壁上的空间投影,并考虑带电粒子在最外闭合磁面外的衰减,最终得到第一壁上带电粒子热流密度分布;The three-dimensional calculation model of the charged particle heat flux density establishes the spatial projection of the charged particles on the first wall according to the plasma configuration and the spatial distribution of the magnetic field, and considers the attenuation of the charged particles outside the outermost closed magnetic surface, and finally obtains the charged particle heat flux on the first wall density distribution;

进行计算时,需已知或能够初步获得以下参数:第一壁材料许用温度T0、第一壁材料辐射度ε、计算工况下的等离子体位形最外闭合磁面空间坐标、第一壁设计结构及空间坐标、聚变堆第一壁的设计保守平均热流密度Q0、磁场空间分布B、工况下衰减长度λq和最后闭合磁力线平行热流密度q0When performing calculations, the following parameters need to be known or can be preliminarily obtained: allowable temperature T0 of the first wall material, radiance ε of the first wall material, space coordinates of the outermost closed magnetic surface of the plasma configuration under calculation conditions, and the first wall The design structure and space coordinates, the design conservative average heat flux Q 0 of the first wall of the fusion reactor, the spatial distribution of the magnetic field B, the decay length λ q under working conditions, and the final closed magnetic flux parallel heat flux q 0 .

本方法计算对象如图2所示,根据已知的托卡马克聚变堆第一壁结构和等离子体最外闭合磁面坐标建立,包括第一壁1、等离子体2;其中第一壁1为马克聚变堆真空室第一壁,根据托卡马克聚变堆设计进行排布,等离子体2为计算工况下位形的最外闭合磁面;The calculation object of this method is shown in Figure 2, which is established according to the known first wall structure of the tokamak fusion reactor and the coordinates of the outermost closed magnetic surface of the plasma, including the first wall 1 and the plasma 2; where the first wall 1 is The first wall of the Mark fusion reactor vacuum chamber is arranged according to the design of the Tokamak fusion reactor, and the plasma 2 is the outermost closed magnetic surface of the configuration under the calculation condition;

本发明方法步骤如图1所示:The inventive method step is as shown in Figure 1:

步骤1,建立辐射换热三维计算模型:根据托卡马克设计中等离子体位形最外闭合磁面空间坐标和第一壁空间坐标建立辐射换热三维计算模型的完整三维结构,根据完整三维结构环向对称性,选取最小重复结构作为计算使用的三维结构,结构如图2所示;Step 1, establish the 3D calculation model of radiation heat transfer: according to the space coordinates of the outermost closed magnetic surface of the plasma configuration and the space coordinates of the first wall in the tokamak design, establish the complete 3D structure of the 3D calculation model of radiation heat transfer, and according to the complete 3D structure loop Toward symmetry, select the minimum repeating structure as the three-dimensional structure used in the calculation, the structure is shown in Figure 2;

辐射换热计算基于有限元法进行离散,辐射换热计算公式采用斯蒂芬-玻耳兹曼定律,辐射发射功率E表达式为:The radiation heat transfer calculation is discrete based on the finite element method, and the radiation heat transfer calculation formula adopts the Stephen-Boltzmann law, and the radiation emission power E expression is:

E=σT4 E=σT 4

其中σ为玻尔兹曼常数;where σ is the Boltzmann constant;

根据热平衡,第一壁辐射热流密度分布qr为对应点总入射辐射热流密度G减去总漫反射热流密度J=ρdG+E(T0)和总镜面反射热流密度ρsG,其中ρd为漫反射系数,ρs为镜面反射系数,并有ε=1-(ρds),最终表达式为:According to heat balance, the radiation heat flux distribution q r of the first wall is the total incident radiation heat flux G minus the total diffuse reflection heat flux J=ρ d G+E(T 0 ) and the total specular reflection heat flux ρ s G at the corresponding point, where ρ d is the diffuse reflection coefficient, ρ s is the specular reflection coefficient, and ε=1-(ρ ds ), the final expression is:

qr=G-(J+ρsG)=ε(E(T)-E(T0))q r =G-(J+ρ s G)=ε(E(T)-E(T 0 ))

式中:E(T)为等离子体辐射发射功率,E(T0)为第一壁辐射发射功率;表达式中选取第一壁材料许用温度T0作为第一壁温度,空间距离与表面法向夹角由三维结构坐标得到,等离子体温度T为未知量,使用迭代法对等离子体温度T进行迭代计算,直到三维结构所有坐标计算得到的qr的平均值与Q0相等,选取此时的第一壁辐射热流密度分布qr作为模型计算结果,如图3所示,从图中可以得到第一壁辐射热流密度空间分布,其数值随坐标变化存在差异,相比使用第一壁辐射热流密度平均值作为热边界本发明计算得到的精细化结果更加准确和保守,降低了计算误差,提高了安全性。In the formula: E(T) is the radiation emission power of the plasma, E(T 0 ) is the radiation emission power of the first wall; in the expression, the allowable temperature T 0 of the first wall material is selected as the temperature of the first wall, and the spatial distance and the surface The normal angle is obtained from the coordinates of the three-dimensional structure, and the plasma temperature T is an unknown quantity. The iterative method is used to iteratively calculate the plasma temperature T until the average value of q r calculated by all coordinates of the three-dimensional structure is equal to Q 0 . The first wall radiative heat flux distribution q r is taken as the calculation result of the model, as shown in Figure 3, the spatial distribution of the first wall radiative heat flux can be obtained from the figure, and its value varies with the coordinate change. Using the average value of radiation heat flux as the thermal boundary, the refined results calculated by the present invention are more accurate and conservative, which reduces calculation errors and improves safety.

步骤2,建立带电粒子热流密度三维计算模型:带电粒子热流密度三维计算模型采用与步骤1相同三维结构;带电粒子热流密度计算采用有限元法进行离散,首先已知磁场空间分布B,通常记录为托卡马克坐标并由各个坐标系下的径向、环向、极向三组数据表示,选取三维结构中每个计算点磁场方向作为其坐标处带电粒子方向,对磁场托卡马克坐标进行笛卡尔坐标代换,表达式为:Step 2, establish a three-dimensional calculation model of charged particle heat flux: the three-dimensional calculation model of charged particle heat flux adopts the same three-dimensional structure as in step 1; the calculation of charged particle heat flux adopts the finite element method for discretization, firstly, the spatial distribution of the magnetic field B is known, usually recorded as The tokamak coordinates are represented by three sets of data in the radial direction, the circumferential direction, and the polar direction in each coordinate system. The magnetic field direction of each calculation point in the three-dimensional structure is selected as the direction of the charged particles at its coordinates, and the magnetic field tokamak coordinates are calculated. Carr coordinate substitution, the expression is:

由于磁场具备环向均匀性,B(r,phi,z)=B(r,z),B(r,phi,z)为随托卡马克坐标变化的磁场,B(r,z)为随托卡马克坐标变化的轴对称磁场;磁场平行热流密度q采用指数衰减模型,表达式为:Since the magnetic field has circumferential uniformity, B(r, phi, z) = B(r, z), B(r, phi, z) is the magnetic field that changes with the coordinates of the tokamak, and B(r, z) is the The axisymmetric magnetic field of the tokamak coordinate change; the parallel heat flux q of the magnetic field adopts the exponential decay model, and the expression is:

其中q为磁场平行热流密度,q0为最后闭合磁力线平行热流密度,d为计算点与最外闭合磁面空间距离,λq为工况下衰减长度;Where q is the heat flux parallel to the magnetic field, q 0 is the heat flux parallel to the last closed magnetic force line, d is the spatial distance between the calculation point and the outermost closed magnetic surface, and λ q is the attenuation length under working conditions;

则第一壁上带电粒子热流密度qb为:Then the heat flux q b of charged particles on the first wall is:

其中n为计算点法向量,nx、ny、nz分别为计算点法向量在笛卡尔坐标系下分量,Bphi、Br、Bz分别为磁场空间分布B在托卡马克坐标系下分量,此时qb为模型计算结果如图4所示,从图中可以得到考虑磁场方向和第一壁夹角并考虑衰减的带电粒子热流密度在第一壁上的分布,可以看出夹角和距离对计算结果的影响,结果更加精确、效率更高,降低了计算误差,提高了效率和安全性。Where n is the normal vector of the calculation point, n x , ny , and nz are the components of the normal vector of the calculation point in the Cartesian coordinate system, B phi , B r , and B z are the magnetic field spatial distribution B in the tokamak coordinate system The lower component, at this time q b is the calculation result of the model, as shown in Figure 4. From the figure, we can get the distribution of the heat flux of charged particles on the first wall considering the direction of the magnetic field and the angle between the first wall and the attenuation. It can be seen that The influence of the included angle and distance on the calculation results, the results are more accurate and efficient, the calculation error is reduced, and the efficiency and safety are improved.

Claims (2)

1. A calculation method for the heat flux density of a first wall of a Tokamak fusion reactor is characterized by comprising the following steps of: the method is based on plasma configuration, magnetic field spatial distribution and first wall spatial distribution, and a radiation heat exchange three-dimensional calculation model and a charged particle heat flux density three-dimensional calculation model are respectively built according to a first wall heat flux density source;
the radiation heat exchange three-dimensional calculation model refers to the conservative average heat flux density of the Tokamak fusion reactor engineering design, iterative calculation is carried out on the plasma temperature, and finally the first wall radiation heat flux density distribution when the average heat flux density is consistent is obtained;
the three-dimensional calculation model of the heat flux density of the charged particles establishes the space projection of the charged particles on the first wall according to the plasma configuration and the magnetic field space distribution, and considers the attenuation of the charged particles outside the outermost closed magnetic surface to finally obtain the heat flux density distribution of the charged particles on the first wall;
the method calculates the object to include the first wall (1), plasma (2); the first wall (1) is arranged according to the design of the tokamak fusion reactor, and the plasma (2) is the outermost closed magnetic surface of the configuration under the working condition;
in performing the calculations, the following parameters need to be known or can be obtained initially: first wall material allowable temperature T 0 Calculating the radiation epsilon of the first wall material, calculating the spatial coordinate of the outermost closed magnetic surface of the plasma configuration under the working condition, the design structure and the spatial coordinate of the first wall, and the design conservation average heat flow density Q of the first wall of the fusion reactor 0 The magnetic field space distribution B and the attenuation length lambda under the working condition q And finally closing the magnetic force line parallel heat flow density q 0
2. The method for calculating the heat flux density of the first wall of the tokamak fusion reactor according to claim 1, wherein the method comprises the following steps: the method comprises the following steps:
step 1, establishing a radiation heat exchange three-dimensional calculation model: establishing a complete three-dimensional structure of a radiation heat exchange three-dimensional calculation model according to the space coordinates of the outermost closed magnetic surface of the plasma configuration and the space coordinates of the first wall in the Tokamak design, and selecting the minimum repeated structure as a three-dimensional structure for calculation according to the circumferential symmetry of the complete three-dimensional structure;
the radiation heat exchange calculation is based on the finite element method, the radiation heat exchange calculation formula adopts the Stefan-Boltzmann law, and the radiation emission power E expression is as follows:
E=σT 4
wherein σ is the boltzmann constant;
according to the heat balance, the first wall radiates the heat flux density distribution q r Subtracting the total diffuse reflected heat flux density j=ρ from the total incident radiant heat flux density G for the corresponding point d G+E(T 0 ) And total specular heat flux density ρ s G, where ρ d Is the diffuse reflection coefficient ρ s Is a specular reflection coefficient and has epsilon=1- (ρ) ds ) The final expression is:
q r =G-(J+ρ s G)=ε(E(T)-E(T 0 ))
wherein: e (T) is the radiation emission power of plasma, E (T) 0 ) Radiating an emission power for the first wall; the allowable temperature T of the first wall material is selected in the expression 0 As the first wall temperature, the space distance and the surface normal angle are obtained by three-dimensional structure coordinates, the plasma temperature T is unknown, and iterative calculation is carried out on the plasma temperature T by using an iterative method until q is obtained by calculating all coordinates of the three-dimensional structure r Average value of (1) and Q 0 Equally, the first wall radiation heat flow density distribution q at this time is selected r As a model calculation result;
step 2, establishing a three-dimensional calculation model of the heat flux density of the charged particles: the three-dimensional calculation model of the heat flux density of the charged particles adopts the same three-dimensional structure as that of the step 1; the method comprises the steps of performing dispersion on the heat flux density of charged particles by adopting a finite element method, firstly knowing the spatial distribution B of a magnetic field, selecting the magnetic field direction of each calculated point in a three-dimensional structure as the charged particle direction at the coordinate position of the calculated point, and performing Cartesian coordinate substitution on the Tokamak coordinate of the magnetic field if the magnetic field is the Tokamak coordinate, wherein the expression is as follows:
since the magnetic field has circumferential uniformity, B (r, phi, z) =b (r, z), B (r, phi, z) is a magnetic field that varies with tokamak coordinates, and B (r, z) is an axisymmetric magnetic field that varies with tokamak coordinates; the parallel heat flux density q of the magnetic field adopts an exponential decay model, and the expression is:
wherein q is the magnetic field parallel heat flux density, q 0 Parallel heat flux density for closing magnetic force lines finallyDegree, d is the spatial distance between the calculated point and the outermost closed magnetic surface, lambda q The attenuation length under the working condition;
the heat flux density q of the charged particles on the first wall b The method comprises the following steps:
where n is the normal vector of the calculated points, n x 、n y 、n z Respectively calculating components of normal vectors of points in a Cartesian coordinate system, B phi 、B r 、B z The spatial distribution B of the magnetic field is respectively the component under the Tokamak coordinate system, q is the moment b Results are calculated for the model.
CN202310698237.0A 2023-06-13 2023-06-13 A Calculation Method of Heat Flux in the First Wall of Tokamak Fusion Reactor Pending CN116522682A (en)

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN119356106A (en) * 2024-12-30 2025-01-24 中国科学院合肥物质科学研究院 A method for optimizing the magnetic control system of a tokamak based on a data-driven model

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