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快堆单个燃料组件完全堵流事故的建模及其验证
Modeling of Accident Scenario Caused by Total Blockage of Single Subassembly in a Fast Reactor and its Validation
【摘要】 为了预测正常功率下快堆单个燃料组件入口完全堵流所导致的事故序列,根据SCARABEE-N系列实验建立了相关的计算模型。冷却剂的沸腾及其两相流动的描述采用两流体模型;包壳的流动、燃料的熔化及其塌陷采用类似SURFASS程序的简单方法处理。对于事故后期形成的UO2-钢混合沸腾池,采用一维半经验模型描述,即:用漂移速度模型来预测空泡份额分布;用修正后的Greene关系式计算沸腾池和壁面之间的传热系数;用焓方法(enthalpy method)求解包裹沸腾池的固化壳的温度场及厚度。为了验证本文建立的模型,对SCARABEE BE+1实验结果进行了校核计算,其结果与实验结果基本吻合。
【Abstract】 In order to predict the accident scenario caused by total inlet blockage of single subassembly at full power in a fast reactor,a calculational model was developed according to SCARABEE-N subassembly melting and propagation tests.In the model,sodium thermal-hydraulics was described by a two-fluid sub-channel model.The motion of melting cladding and melting fuel was dealt with very simple approach similar to that of SURFASS code.The behavior of UO2-steel mixed boiling pool was determined by a one dimen-sional semi-empirical model,in which the distribution of void fraction was calculated by drift flux model,heat transfer coefficient between the boiling pool and the wall was determined by modified Greene correla-tion,the temperature field and thickness of solidified UO2 crust were obtained by solving enthalpy model.Calculation for SCARABEE BE+1 experiment was performed to validate the model,the results approxi-mately agree with the experimental observation.
- 【文献出处】 核动力工程 ,Nuclear Power Engineering , 编辑部邮箱 ,2006年01期
- 【分类号】TL352
- 【被引频次】7
- 【下载频次】168