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作 者:赵树峰[1] 罗锐[1] 石晓波[1] 王洲[1] 杨献勇[1]
机构地区:[1]清华大学热科学与动力工程教育部重点实验室,北京100084
出 处:《核科学与工程》2007年第3期198-205,共8页Nuclear Science and Engineering
摘 要:快堆在超设计基准事故下运行,会导致燃料元件的熔化,并很快形成燃料和钢的混合沸腾池,池壁破损之后,高温熔融物将向组件盒间隙以及相邻组件中传播,使事故进一步升级。为了弄清熔融物传播的机理,采用了机理建模的方法,分别建立了导热冻结和整体冻结两种机理模型,在英国的SES实验及法国的PV-A实验上进行了验证,得出了有关冻结机理和钠流动的相关结论,通过对传播的相关参数进行比较分析,得出了熔融物传播的相关结论。Under severe accidental condition in one subassembly of the fast reactor, the pins will be molten and soon the boiling pool of fuel and steel will be formed. After the wrapper of the pool is melt-through, it is propagation of molten material into the gap and neighbor subassemblies that upgrades the accident. To make the penetration mechanism of molten materials clear, a method of establishing model according to the mechanism is selected. Conduction freezing and bulk freezing model are established separately, and they are validated on the UK SES experiment and France PV-A experiment. On the basis of validation, some conclusion about the freezing mechanism and the sodium flow is derived. After comparing and analyzing the parameters about the penetration, some conclusions about the penetration are derived as well.
分 类 号:TL433[核科学技术—核技术及应用]
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