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Experimental Research on High-Temperature Thermo-mechanical Behavior of Self-Developed New Type Zirconium Cladding Under Loss-of-Coolant Accident
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Affiliation:

1.Xi'an Jiaotong University, Xi'an 710049, China;2.National Key Laboratory of Nuclear Reactor Technology, Nuclear Power Institute of China, Chengdu 610041, China

Clc Number:

TL341;TG146.4+14

Fund Project:

] Romano Y, Patterson E, Candes E. Advances in Neural Information Processing Systems[C]. Vancouver: NIPS Foundation, 2019: 32

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    Abstract:

    High-temperature thermo-mechanical experiments were conducted to investigate the behavior of self-developed new type zirconium cladding under loss-of-coolant accident (LOCA) conditions, including high-temperature oxidation, high-temperature creep, high-temperature burst, and embrittlement experiment. Results show that the high-temperature oxidation rate of self-developed new type zirconium cladding is comparable to that of ZIRLO, M5, and Zr-4 cladding when the oxidation temperature exceeds 1000 °C, which can be estimated by Cathcart-Pawel model. Notably, the self-developed new type zirconium cladding exhibits significantly lower high-temperature creep-burst strain than M5 and Zr-4 cladding, which can decrease fuel assembly blockage during LOCA, thus contributing to a more favorable outcome in LOCA analysis. Additionally, the embrittlement criteria of the self-developed new type zirconium cladding meet the requirements of a peak cladding temperature of ≤1204 ℃ and the maximum cladding oxidation rate of ≤17%.

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[Guo Xiaoming, Qian Libo, Luo Yuejian. Experimental Research on High-Temperature Thermo-mechanical Behavior of Self-Developed New Type Zirconium Cladding Under Loss-of-Coolant Accident[J]. Rare Metal Materials and Engineering,2025,54(7):1802~1809.]
DOI:10.12442/j. issn.1002-185X.20240727

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History
  • Received:November 07,2024
  • Revised:April 08,2025
  • Adopted:April 10,2025
  • Online: July 01,2025
  • Published: June 23,2025