Development of System Analysis Code for Sodium-cooled Fast Reactor and its Verification on SHRT-45R Benchmark Problem
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摘要: 基于最佳估算方法的钠冷快堆的系统分析软件对于反应堆系统设计和安全审评都至关重要。本研究从底层开发适用于通用堆型的钠冷快堆系统分析软件FRTAC，在卡式输入的基础上，加入图形化界面，并通过软件内部测试和第三方测试，计算功能可以覆盖反应堆正常运行、瞬态运行、设计基准工况和部分设计扩展工况。为验证FRTAC计算的准确性，采用国际原子能机构SHRT-45R基准题进行建模与分析，结果证明堆芯冷却剂温度、流量等关键参数与实验值误差均小于10%，FRTAC计算结果准确，可用于钠冷快堆的事故分析。
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关键词:
- 钠冷快堆 /
- FRTAC；系统分析 /
- SHRT-45R基准题
Abstract: The system analysis software for sodium-cooled fast reactors based on best estimation methods is crucial for both reactor system design and safety review. In this study, the Fast Reactor Transient Analysis Code（FRTAC） of sodium-cooled fast reactor system suitable for general reactor type is developed. Besides traditional input card, a graphical user interface is added. Through internal testing and third-party testing, FRTAC simulation function can cover the normal operation, transient operation, design basis conditions and some design extended conditions. In order to verify the accuracy of the software, the International Atomic Energy Agency SHRT-45R benchmark problems were used for modeling and analysis. The results prove that the errors of key parameters such as core coolant temperature and flow rate between calculation results and experimental values were less than 10%. The FRTAC calculation results of the software are accurate and can be used for accident analysis of sodium-cooled fast reactor. -
图 5 SHRT-45R Z型管进口温度
Figure 5. Inlet Coolant Temperature of Z-shape Heat Transfer Tubes of SHRT-45R
表 1 EBR-Ⅱ设计参数
Table 1. Design Parameters of EBR-Ⅱ
参数 参数值 额定热功率/MW 62.5 额定电功率/MW 20 一回路额定钠流量/(kg· s−1) 485 中间回路额定钠流量/(kg· s−1) 315 钠池容积/m3 340 
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