Preliminary Study on Heating Rate Calculation for PWR Internals by Three-Dimensional S<sub>N</sub> Method

YANG Shouhai; CHEN Yixue; WANG Weijin; JIN Zhongmin; LU Daogang

Mar. 2025

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Article Navigation > Nuclear Power Engineering > 2012 > 33(1): 25-28

YANG Shouhai, CHEN Yixue, WANG Weijin, JIN Zhongmin, LU Daogang. Preliminary Study on Heating Rate Calculation for PWR Internals by Three-Dimensional SN Method[J]. Nuclear Power Engineering, 2012, 33(1): 25-28.

Citation:

YANG Shouhai, CHEN Yixue, WANG Weijin, JIN Zhongmin, LU Daogang. Preliminary Study on Heating Rate Calculation for PWR Internals by Three-Dimensional S_N Method[J]. Nuclear Power Engineering, 2012, 33(1): 25-28.

Citation:

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Preliminary Study on Heating Rate Calculation for PWR Internals by Three-Dimensional S_N Method

1. School of Nuclear Science and Engineering, North China Electric Power University, Beijing, 102206, China;
2. State Nuclear Power Software Development Center, Beijing, 100029, China

Received Date: 2010-09-26
Rev Recd Date: 2011-07-08

Available Online: 2025-03-08

Abstract

Abstract

Based on the American H.B.Robinson-2 pressure vessel benchmark,the neutron spectrum in surveillance capsule and reaction rates for some species have been obtain by three-dimensional（3-D） discrete ordinates（SN） method code（TORT）.The results show that,the neutron spectrum in surveillance capsule makes good agreement with the benchmark,and the C/M of reaction rates for some species is 1.04±0.04 by TORT code.Then,the heat release rate distribution over reactor components has been calculated by TORT code and MCNP program for Ningde Nuclear Power Plant in Fujian China,and compared with each other.Finally,the application of TORT code in the calculation of the heating rate for PWR internals is presented and discussed.
- Three-dimensional discrete-ordinates method,
- H.B.Robinson-2 benchmark,
- Reactor inter-nals,
- Heating rate