Author:
Zheng Qi,Shen Wei,Li Xuesong,Hao Tengfei,He Qingming,Li Jie,Liu Zhouyu
Abstract
The ex-core detector-response calculation is a typical deep-penetration problem, which is challenging for the Monte Carlo method. The response of the ex-core detector is an important parameter for the safe operation of the nuclear power plants. Meanwhile, evaluation of the ex-core detector response during each step of fuel-loading is used to guide the fuel-loading sequence. The response can also be used to reconstruct core-power distribution for online monitoring of long-term power. The detector used for the ex-core response is the source-range detector which is sensitive to thermal neutrons. For a Monte Carlo shielding calculation of the above detector response, the thermal flux under 0.625eV is needed, which is too small to be tallied by traditional Monte Carlo simulations. In practice, the tally results are close to zero in the detector region under direct Monte Carlo calculation. Even if the number of particles is increased to a significant amount, the statistical variance is still very large. The high variance along with a significant calculation time leads to a small Figure Of Merit (FOM). In order to solve this problem and to improve the tally efficiency of the ex-core detector response, a hybrid Monte-Carlo-deterministic method is employed in this study, and an in-house hybrid Monte-Carlo-deterministic particle transport code, NECP-MCX, is developed in this paper. The method takes the space-energy-dependent adjoint fluxes to generate importance parameters for the mesh-based weight window in the Monte Carlo calculation. Simultaneously, the mesh-based source biasing is performed with the consistent importance parameters to make the starting weight of neutrons matching with the survival weight of the weight windows. As the mesh used in the hybrid Monte-Carlo-deterministic method is superimposed, the mesh of the weight window will not be affected by the complex geometry model. The adjoint flux is obtained by the efficient SN method with the multi-group cross-section data. The whole toolset is convenient to use with single set of the modelling data for both Monte Carlo and deterministic simulations. Compared with the direct Monte Carlo simulation, the hybrid Monte-Carlo-deterministic method has a higher efficiency for a typical deep-penetration problem such as the AP1000 ex-core detector-response simulation.
Reference8 articles.
1. Experimental and theoretical study of BF 3 detector response for thermal neutrons in reflecting materials
2. Qianxue Ding, Qiliang Mei, Wentao Li, Mengqi Wang, Yan Zhou, Guodong Ye. Analysis and Research of Ex-core Source Range Detector Count Rate in PWR Nuclear Power. Journal of North China Electric Power University,39(2012)
3. Westinghouse Electric Company. Zero Power Physics Test Simulations for the AP1000 PWR. 2014.
4. Baker R.S.. “An SN Algorithm for Modern Architectures.” Nuclear Science and Engineering, 185.1(2017).
5. Development of a new parallel S N code for neutron-photon transport calculation in 3-D cylindrical geometry
Cited by
2 articles.
订阅此论文施引文献
订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献