首页|基于MOOSE平台的燃料元件锆合金高温氧化行为研究

基于MOOSE平台的燃料元件锆合金高温氧化行为研究

Research on High Temperature Oxidation Behavior of Zirconium Alloy for Fuel Element Based on MOOSE Platform

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为建立新型N36锆合金高温氧化行为预测方法,使得自主燃料元件性能分析程序FORWARD能适用于失水事故(LOCA)工况.本研究开展了新型N36锆合金高温蒸汽氧化试验,建立了 N36锆合金高温氧化模型并对其进行了验证,最后基于FORWARD程序对LOCA工况下N36锆合金的高温氧化行为进行预测.结果表明,预测得到的N36锆合金的氧化增重与验证试验结果较为符合,且预测的N36锆合金在LOCA工况下的高温氧化行为较为合理.因此,本研究建立的模型和燃料元件性能分析程序能够用于新型N36锆合金高温氧化行为的预测.
In order to establish a prediction method for the high-temperature oxidation behavior of the new N36 zirconium alloy and allow the autonomous fuel element performance analysis code FORWARD to be applied to the loss of coolant accident(LOCA)condition,the high-temperature steam oxidation test of the new N36 zirconium alloy was carried out in this study.The high-temperature oxidation model of N36 zirconium alloy was developed and validated,and the high-temperature oxidation behavior of N36 zirconium alloy under LOCA condition was predicted using the FORWARD code.The results show that the predicted oxidation weight gain of N36 zirconium alloy is in good agreement with the verification test results,and the predicted oxidation behavior of N36 zirconium alloy at high temperature under LOCA condition is reasonable.Therefore,the model and fuel element performance analysis code developed in this study can be used to predict the high temperature oxidation behavior of the new N36 zirconium alloy.

N36 zirconium alloyHigh temperature oxidationMOOSEFORWARD code

邬周志、张坤、王严培、余红星、张林、何梁、唐昌兵

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中国核动力研究设计院核反应堆系统设计技术重点实验室,成都,610213

N36锆合金 高温氧化 MOOSE FORWARD程序

国家自然科学基金国家自然科学基金四川省自然科学基金四川省自然科学基金中核集团青年科技创新团队项目

U1867219U20672212023NSFSC13162022NSFSC1953

2024

核动力工程
中国核动力研究设计院

核动力工程

CSTPCD北大核心
影响因子:0.3
ISSN:0258-0926
年,卷(期):2024.45(1)
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