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失水事故工况自主化新型锆合金包壳
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1.西安交通大学,中国核动力研究设计院;2.中国核动力研究设计院 核反应堆技术全国重点实验室 成都

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国家科技部重点研发计划(2022YFB1902400)


Experimental Research on High-temperature Thermo-mechanical Behavior of Self-Developed New Type Zirconium Cladding under Loss-of-Coolant Accident
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1.Xi&2.amp;3.#39;4.&5.an Jiaotong University,Nuclear Power Institute of China;6.Nuclear Power Institute of China, National Key Laboratory of Nuclear Reactor Technology

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    摘要:

    本文针对自主化新型锆合金包壳开展了失水事故工况高温热-机械行为特性试验,包括高温氧化、高温塑性变形、高温爆破以及脆化失效等,获得了自主化锆合金包壳失水事故关键行为特性。自主化新型锆合金包壳高温氧化试验结果显示,在氧化温度高于1000℃工况下,自主化锆合金包壳高温氧化速率与ZIRLO、M5及Zr-4包壳相当,且可采用Cathcart-Pawel氧化模型估算;自主化新型锆合金包壳高温塑性变形试验和高温爆破试验结果显示,自主化锆合金包壳高温爆破温度略低于高温塑性变形爆破温度,自主化新型锆合金包壳高温塑性变形爆破应变显著低于M5及Zr-4包壳,这大大降低了失水事故过程中燃料组件阻塞率,有利于缓解失水事故结果;自主化新型锆合金包壳脆化失效试验结果显示,自主化锆合金包壳脆化失效准则满足“峰值包壳温度≤1204℃&最大包壳氧化率≤17%”要求。

    Abstract:

    High-temperature thermo-mechanical experimentswere conducted to investigate the behaviors 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. The high-temperature oxidation 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 temperatureexceeds1000°C, which could be estimated by Cathcart-Pawel model. Notably, the self-developed new type Zirconium cladding exhibits significantly lower high-temperature creepburst strain M5 and Zr-4 cladding, which could decrease fuel assembly blockage during LOCA accident, thus contributing to a more favorable outcome in LOCA analysis. Additionally, the embrittlementcriteria for Zirconium cladding, “peak cladding temperature ≤ 1204℃ equivalent cladding reacted ≤ 17%”, remains applicable to the self-developed new typeZirconium cladding.

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郭晓明,钱立波,罗跃建.失水事故工况自主化新型锆合金包壳[J].稀有金属材料与工程,,().[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,,().]
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  • 收稿日期:2024-11-07
  • 最后修改日期:2025-04-08
  • 录用日期:2025-04-10
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