摘要
快中子反应堆二氧化铀燃料元件在高燃耗、高中子注量率、高线功率和高温状况下运行,燃料与包壳材料会发生复杂的物理化学相互作用。燃料元件化学相互作用模型的建立对高燃耗快堆燃料元件的设计非常重要。针对快中子反应堆氧化物燃料元件与包壳材料发生的化学相互作用,采用动力学模型建立了二氧化铀与奥氏体不锈钢、铁素体-马氏体钢包壳材料的化学相互作用模型,并通过实验数据验证该模型。结果表明:建立的快堆二氧化铀燃料与奥氏体不锈钢的腐蚀模型可以成功预测最大燃耗10.8at%、辐照损伤87.5 dpa的包壳腐蚀;建立的快堆二氧化铀燃料与铁马钢的腐蚀模型可以成功预测最大燃耗9.3at%、辐照损伤76.6 dpa的包壳腐蚀。研究结果为高燃耗二氧化铀辐照元件及示范快堆燃料元件的设计和性能预测提供重要的参考价值。
[Background] Uranium dioxide fuel elements of fast neutron reactor operate under the conditions of high burnup, high neutron fluence rate, high line power and high temperature. Complex physical chemical interactions occur between fuel and the cladding materials. The establishment of fuel element chemical interaction model is very important for the design of high burnup fast reactor fuel element. [Purpose] This study aims to establish a chemical interaction model between fast reactor fuel and cladding materials under high burnup.[Methods] Emphasis was placed on the chemical interaction phenomenon of the oxide fuel elements of fast neutron reactors. Firstly, the chemical interaction models of uranium dioxide interacted with austenitic stainless steel and ferritic-martensitic steel cladding materials were established by using a dynamic model. Then, special fuel element performance analysis program FIBER-Oxide, developed by China Institute of Atomic Energy(CIAE), was employ to verify these chemical interaction models by experimental data. [Results] The corrosion model of fast reactor uranium dioxide fuel and austenitic stainless steel can successfully predict the cladding corrosion with maximum burnup of 10.8 at% and irradiation damage of 87.5 dpa. The corrosion model of fast reactor uranium dioxide fuel and ferriticmartensitic steel can successfully predict the cladding corrosion with maximum burnup of 9.3 at% and irradiation damage of 76.6 dpa. [Conclusions] The results of this study provide important reference value for the design and performance prediction of high burnup uranium dioxide irradiation elements and fuel elements of demonstration fast reactor.
作者
陈启董
高付海
CHEN Qidong;GAO Fuhai(China Institute of Atomic Energy,Beijing 102413,China)
出处
《核技术》
CAS
CSCD
北大核心
2022年第1期80-86,共7页
Nuclear Techniques
基金
国防科技工业局"堆芯组件设计与验证"项目(No.149601)资助。
关键词
快堆燃料元件
芯块包壳相互作用
腐蚀开裂
高燃耗
Fast reactor fuel element
Pellet cladding interaction
Corrosion cracking
High burnup
作者简介
第一作者:陈启董,男,1991 年出生,2015 年于清华大学获硕士学位,研究领域为快堆燃料元件。
