A sub-critical wait-time experiment to validate stochastic nuclear reactor kinetics models for low neutron source Nuclear Power Plant (NPP) start-up simulations

被引:3
作者
Gordon, T. L. [1 ]
Williams, M. M. R. [1 ]
Eaton, M. D. [1 ]
Haigh, P. [2 ]
Morgan, G. O. [2 ]
Bean, P. S. [2 ]
机构
[1] Imperial Coll London, Dept Mech Engn City & Guilds Bldg, Nucl Engn Grp, Exhibit Rd,South Kensington Campus, London SW72BX, England
[2] Rolls Royce PLC, POB 2000, Derby DE217XX, Derby, England
基金
英国工程与自然科学研究理事会;
关键词
P & aacute; l-Bell; Cumulative distribution function; CALLISTO-SPK; Wait time probability distribution; Stochastic nuclear reactor kinetics; PROBABILITY-DISTRIBUTION; MONTE-CARLO; INITIATION; DISTRIBUTIONS; PRECURSORS; UNIVERSITY; CODE;
D O I
10.1016/j.pnucene.2024.105268
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The aim of this paper is to present a theoretical sub -critical wait -time experiment that may be used to validate stochastic nuclear reactor kinetics models which compute the neutron population probability distribution. The regulation governing many zero -power reactors prohibits super -critical nuclear reactor operation. This paper shows that a desirable wait -time probability distribution can be computed by only modifying the neutron source strength. An analytical model, which ignores the contribution of delayed neutron precursors, is presented. Additionally, a six -delayed neutron precursor group model using the P & aacute;l-Bell equations is used to investigate the relationship between the nuclear reactor system parameters and the resulting wait -time probability distribution. Finally, this paper shows that two neutron energy group models can be collapsed down to an equivalent single (one speed or mono -energetic) neutron energy group model which accurately reproduce the same wait -time probability distribution.
引用
收藏
页数:15
相关论文
共 69 条
[51]   Improvement of neutron startup source handling work by developing new transportation container for high-temperature engineering test reactor (HTTR) [J].
Shimazaki, Yosuke ;
Sawahata, Hiroaki ;
Shinohara, Masanori ;
Yanagida, Yoshinori ;
Kawamoto, Taiki ;
Takada, Shoji .
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2017, 54 (02) :260-266
[52]   Coupling of dynamic Monte Carlo with thermal-hydraulic feedback [J].
Sjenitzer, Bart L. ;
Hoogenboom, J. Eduard ;
Escalante, Javier Jimenez ;
Espinoza, Victor Sanchez .
ANNALS OF NUCLEAR ENERGY, 2015, 76 :27-39
[53]   The equivalent fundamental-mode source [J].
Spriggs, GD ;
Busch, RD ;
Sakurai, T ;
Okajima, S .
ANNALS OF NUCLEAR ENERGY, 1999, 26 (03) :237-264
[54]   Simulations of the source-range detector response for the fuel-loading process of the AP1000 cores [J].
Sun, Bin ;
Li, Yunzhao ;
Cao, Liangzhi ;
Li, Xuesong ;
Wu, Hongchun ;
Shen, Wei ;
Hao, Tengfei ;
Wan, Chenghui .
NUCLEAR ENGINEERING AND DESIGN, 2021, 372
[55]  
SUTTON T. M., 2017, INT C MATH COMP METH
[56]  
Tucker C., 2019, How to Drive a Nuclear Reactor
[57]  
Valentine Frank A., 1963, A Manual of Experiments in Reactor Physics
[58]  
Wakabayashi G., 2023, Introduction to Nuclear Reactor Experiments, P87
[59]  
Walley S.P., 2016, Research Reactors Fuel Management
[60]   The relationship between the backward and forward equations of stochastic neutron transport and associated matters [J].
Williams, M. M. R. .
ANNALS OF NUCLEAR ENERGY, 2023, 186