Development of System Analysis Code for Sodium-cooled Fast Reactor and its Verification on SHRT-45R Benchmark Problem

Sun Lin; Wu Zongyun; Zhang Zhenyu; Xue Fangyuan; Wang Xuesong; Liu Tiancai

doi:10.13832/j.jnpe.2024.S1.0063

Volume 45 Issue S1

Jun. 2024

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Article Navigation > Nuclear Power Engineering > 2024 > 45(S1): 63-67

Sun Lin, Wu Zongyun, Zhang Zhenyu, Xue Fangyuan, Wang Xuesong, Liu Tiancai. Development of System Analysis Code for Sodium-cooled Fast Reactor and its Verification on SHRT-45R Benchmark Problem[J]. Nuclear Power Engineering, 2024, 45(S1): 63-67. doi: 10.13832/j.jnpe.2024.S1.0063

Citation:

Sun Lin, Wu Zongyun, Zhang Zhenyu, Xue Fangyuan, Wang Xuesong, Liu Tiancai. Development of System Analysis Code for Sodium-cooled Fast Reactor and its Verification on SHRT-45R Benchmark Problem[J]. Nuclear Power Engineering, 2024, 45(S1): 63-67. doi: 10.13832/j.jnpe.2024.S1.0063

Citation:

Sun Lin, Wu Zongyun, Zhang Zhenyu, Xue Fangyuan, Wang Xuesong, Liu Tiancai. Development of System Analysis Code for Sodium-cooled Fast Reactor and its Verification on SHRT-45R Benchmark Problem[J]. Nuclear Power Engineering, 2024, 45(S1): 63-67. doi: 10.13832/j.jnpe.2024.S1.0063

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Development of System Analysis Code for Sodium-cooled Fast Reactor and its Verification on SHRT-45R Benchmark Problem

doi: 10.13832/j.jnpe.2024.S1.0063

Department of Nuclear Design and Research, China Institute of Atomic Energy, Beijing, 102413, China

Received Date: 2023-10-21
Rev Recd Date: 2024-01-01
Publish Date: 2024-06-15

Abstract

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.
- Sodium-cooled fast reactor,
- FRTAC, System analysis,
- SHRT-45R benchmark problem

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References

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