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首页> 外文期刊>Progress in Nuclear Energy >Reconstruction of neutron flux distribution by nodal synthesis method using online in-core neutron detector readings
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Reconstruction of neutron flux distribution by nodal synthesis method using online in-core neutron detector readings

机译：使用在线核心中子探测器读数通过Nodal合成方法重建中子磁通量分布

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摘要

The safety and optimal performance of nuclear reactors require online monitoring in the core. The present paper describes a method that avoids the solution of the time-dependent neutron diffusion equation, and it uses online readings of the fixed in-core neutron detectors to reconstruct the three-dimensional (3D) neutron flux distribution. The essential idea of the nodal synthesis method is the separation of time and space-dependence of the neutron flux distribution. The time-dependent section of the flux distribution is determined by in-core neutron detector readings, and the space-dependent section is obtained from pre-computed harmonics of the neutron diffusion equation. In online computation, time-dependent coefficients are only computed, and flux distribution is reconstructed by pre-computed harmonics. To calculate the diffusion equation harmonics, the nodal expansion method and the Gram-Schmidt process are used. Online reconstruction of neutron flux distribution in the Bushehr Nuclear Power Plant with VVER-1000/446 reactor type is simulated, and the results are benchmarked by valid results. The maximum relative percent error between reconstructed results and the valid results is about 5%, and the computing time is about 0.5 s.
机译：核反应堆的安全性和最佳性能需要在线监测核心。本文介绍了一种避免时间依赖中子扩散方程的解决方案的方法，并且它使用固定核心中子检测器的在线读数来重建三维（3D）中子磁通量分布。节点合成方法的基本思想是中子磁通量分布的时间和空间依赖性的分离。磁通量分布的时间依赖性部分由核心中子检测器读数确定，并且空间依赖性部分是从中子扩散方程的预计算谐波获得的。在在线计算中，仅计算时间相关系数，并且通过预计算机谐波重建通量分布。为了计算扩散方程谐波，使用节点扩展方法和克施密特过程。模拟了Bushr核电站中子通量分布的在线重建，采用VVER-1000/446反应堆类型，结果是通过有效结果的基准测试。重建结果和有效结果之间的最大相对百分比误差为约5％，计算时间约为0.5秒。

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