Safety Analysis on Accident-tolerant Fuel during LBLOCA Based on LOCUST Code

Xiong Yiran; Ma Zehua; Liang Ren; Lin Zhikang; Ju Zhongyun; Peng Zhenxun

doi:10.13832/j.jnpe.2024.S1.0138

Volume 45 Issue S1

Jun. 2024

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Article Navigation > Nuclear Power Engineering > 2024 > 45(S1): 138-144

Xiong Yiran, Ma Zehua, Liang Ren, Lin Zhikang, Ju Zhongyun, Peng Zhenxun. Safety Analysis on Accident-tolerant Fuel during LBLOCA Based on LOCUST Code[J]. Nuclear Power Engineering, 2024, 45(S1): 138-144. doi: 10.13832/j.jnpe.2024.S1.0138

Citation:

Xiong Yiran, Ma Zehua, Liang Ren, Lin Zhikang, Ju Zhongyun, Peng Zhenxun. Safety Analysis on Accident-tolerant Fuel during LBLOCA Based on LOCUST Code[J]. Nuclear Power Engineering, 2024, 45(S1): 138-144. doi: 10.13832/j.jnpe.2024.S1.0138

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Safety Analysis on Accident-tolerant Fuel during LBLOCA Based on LOCUST Code

doi: 10.13832/j.jnpe.2024.S1.0138

China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen, Guangdong, 518000, China

Received Date: 2023-05-20
Rev Recd Date: 2024-04-15
Publish Date: 2024-06-15

Abstract

Abstract

Accident tolerant fuel (ATF) aims to improve the safety characteristics of nuclear fuel under normal operating conditions and accidents. In order to evaluate the safety performance of ATF in large break loss-of-coolant accident (LBLOCA) of large commercial pressurized water reactor, based on LOCUST code, this study analyzes and describes the main thermal hydraulic phenomena and key influencing parameters of HPR1000 using using UO₂-Cr coated zirconium alloy cladding fuel at different stages of LBLOCA. The results indicate that compared to the traditional UO₂-Zr fuel, UO₂-Cr coated zirconium alloy cladding fuel can reduce the peak cladding temperature (PCT) and the thickness of cladding oxide film under LBLOCA, improve the safety margin in accidents, and have better accident-tolerance characteristics.
- Accident tolerant fuel,
- Large break loss-of-coolant accident,
- HPR1000,
- Safety analysis

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References(12)

References

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