超临界水冷堆系统分析程序开发

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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

摘要: 详细介绍了自主开发的超临界水堆(SCWR)安全分析程序SCTRAN的数学模型、辅助方程及计算流程。运用圆管内超临界水的喷放实验数据和西屋公司SCWR大破口失水事故(LOCA)数据对SCTRAN程序的有效性进行验证。验证结果表明,SCTRAN计算结果与程序APROS基本一致,对西屋公司SCWR非能动冷却剂系统的事故分析结果同RELAP5-3D程序的结果基本一致,计算结果可靠性较高,具备对SCWR进行事故分析的能力。
- 超临界水堆 /
- 系统分析程序 /
- 非能动安全系统 /
- 失水事故
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.