Development of Deterministic Code System for GFR Depletion Calculation

ZHANG Jing-yu; SUN Yu-liang; LI Fu; YAN Jian-qiu

Dec. 2010

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Article Navigation > Nuclear Power Engineering > 2010 > 31(S2): 68-72

ZHANG Jing-yu, SUN Yu-liang, LI Fu, YAN Jian-qiu. Development of Deterministic Code System for GFR Depletion Calculation[J]. Nuclear Power Engineering, 2010, 31(S2): 68-72.

Citation:

ZHANG Jing-yu, SUN Yu-liang, LI Fu, YAN Jian-qiu. Development of Deterministic Code System for GFR Depletion Calculation[J]. Nuclear Power Engineering, 2010, 31(S2): 68-72.

ZHANG Jing-yu, SUN Yu-liang, LI Fu, YAN Jian-qiu. Development of Deterministic Code System for GFR Depletion Calculation[J]. Nuclear Power Engineering, 2010, 31(S2): 68-72.

Citation:

ZHANG Jing-yu, SUN Yu-liang, LI Fu, YAN Jian-qiu. Development of Deterministic Code System for GFR Depletion Calculation[J]. Nuclear Power Engineering, 2010, 31(S2): 68-72.

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Development of Deterministic Code System for GFR Depletion Calculation

1. Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing, 100084, China;
2. China Nuclear Power Engineering Company, Beijing, 100840, China

Received Date: 2010-09-20
Rev Recd Date: 2010-10-25

Available Online: 2025-07-31

Abstract

Abstract

In order to solve the depletion problem of Gas-Cooled Fast Reactor（GFR） quickly and accurately,a deterministic code system is developed.Based on the general compution framework of depletion process,some codes for data conversion,cross section regulation,depletion interpolation and automatic control,are programmed and used to couple the transport code WIMS and diffusion code CITATION.The simulation of the depletion process of one GFR model shows that the deterministic code system is feasible,and it is capable to analyze the neutronics characteristics during the depletion process of GFR.
- Gas-Cooled Fast Reactor,
- Deterministic method,
- Code system,
- Depletion