Development of Safety Analysis Code for SCWR

WU Pan; DANG Gao-jian; GOU Jun-li; DAN Jian-qiang; JIANG Yang; ZHANG Bo; LI Xiang

Mar. 2025

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Article Navigation > Nuclear Power Engineering > 2013 > 34(1): 92-96

WU Pan, DANG Gao-jian, GOU Jun-li, DAN Jian-qiang, JIANG Yang, ZHANG Bo, LI Xiang. Development of Safety Analysis Code for SCWR[J]. Nuclear Power Engineering, 2013, 34(1): 92-96.

Citation:

WU Pan, DANG Gao-jian, GOU Jun-li, DAN Jian-qiang, JIANG Yang, ZHANG Bo, LI Xiang. Development of Safety Analysis Code for SCWR[J]. Nuclear Power Engineering, 2013, 34(1): 92-96.

WU Pan, DANG Gao-jian, GOU Jun-li, DAN Jian-qiang, JIANG Yang, ZHANG Bo, LI Xiang. Development of Safety Analysis Code for SCWR[J]. Nuclear Power Engineering, 2013, 34(1): 92-96.

Citation:

WU Pan, DANG Gao-jian, GOU Jun-li, DAN Jian-qiang, JIANG Yang, ZHANG Bo, LI Xiang. Development of Safety Analysis Code for SCWR[J]. Nuclear Power Engineering, 2013, 34(1): 92-96.

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Development of Safety Analysis Code for SCWR

1 School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, 710049, China;
2. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610041, China

Received Date: 2012-10-15
Rev Recd Date: 2012-11-10

Available Online: 2025-03-08

Abstract

Abstract

This paper introduces the numerical models,auxiliary models and calculation method of code SCTRAN,which is a safety analysis code for SCWR which is developed by ourselves.The simulation of blowdown experiment at supercritical pressure and the LOCA analysis of American SCWR are conducted by the code.By comparing with APROS code and RELAP5-3D code,we can find that the simulation results of SCTRAN agree approximately well with the public recognized code for SCWR.The results indicate that code SCTRAN is capable of carrying out safety analysis for SCWR and its results are reliable.
- SuperCritical Water cooled Reactor（SCWR）,
- System analysis code,
- Passive safety system,
- Loss of coolant accident.