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Domain decomposition methods for the neutron diffusion problem

机译:中子扩散问题的区域分解方法

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The neutronic simulation of a nuclear reactor core is performed using the neutron transport equation, and leads to an eigenvalue problem in the steady-state case. Among the deterministic resolution methods, simplified transport (SP_N) or diffusion approximations are often used. The MINOS solver developed at CEA Saclay uses a mixed dual finite element method for the resolution of these problems, and has shown his efficiency. In order to take into account the heterogeneities of the geometry, a very fine mesh is generally required, and leads to expensive calculations for industrial applications. In order to take advantage of parallel computers, and to reduce the computing time and the local memory requirement, we propose here two domain decomposition methods based on the MINOS solver. The first approach is a component mode synthesis method on overlapping subdomains: several eigenmodes solutions of a local problem on each subdomain are taken as basis functions used for the resolution of the global problem on the whole domain. The second approach is an iterative method based on a non-overlapping domain decomposition with Robin interface conditions. At each iteration, we solve the problem on each subdomain with the interface conditions given by the solutions on the adjacent subdomains estimated at the previous iteration. Numerical results on parallel computers are presented for the diffusion model on realistic 2D and 3D cores.
机译:使用中子输运方程对核反应堆堆芯进行中子模拟,在稳态情况下会导致特征值问题。在确定性解析方法中,通常使用简化传输(SP_N)或扩散近似。 CEA Saclay开发的MINOS解算器使用混合双有限元方法解决了这些问题,并证明了他的效率。为了考虑几何形状的不均匀性,通常需要非常精细的网格,并且导致工业应用的昂贵计算。为了利用并行计算机的优势,并减少计算时间和本地内存需求,我们在此提出了两种基于MINOS求解器的域分解方法。第一种方法是在重叠子域上的组件模式综合方法:每个子域上局部问题的几种本征模式解被用作用于在整个域上解决全局问题的基础函数。第二种方法是基于具有Robin接口条件的非重叠域分解的迭代方法。在每次迭代中,我们使用在前一次迭代中估计的相邻子域上的解所给出的接口条件来解决每个子域上的问题。给出了在并行2D和3D核上的扩散模型的并行计算机上的数值结果。

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