Development of an Evaluation Methodology for Fuel Discharge in Core Disruptive Accidents of Sodium-Cooled Fast Reactors  

作　　者：Kenji Kamiyama Yoshiharu Tobita Tohru Suzuki Ken-ichi Matsuba 

机构地区：[1]Japan Atomic Energy Agency, Ibaraki 311-1393, Japan

出　　处：《Journal of Energy and Power Engineering》2014年第5期785-793,共9页能源与动力工程（美国大卫英文）

摘　　要：The purpose of the present study is to develop a methodology to evaluate fuel discharge through the CRGT （control-rod guide tube） during CDAs （core-disruptive accidents） of SFRs （sodium-cooled fast reactors）, since fuel discharge will decrease the core reactivity and CRGTs have a potential to provide an effective discharge path. Fuel discharge contains multi-component fluid dynamics with phase changes, and, in the present study, the SFR safety analysis code SIMMER （Sn, implicit, multifield, multicomponent, Eulerian recriticality） was utilized as a technical basis. First, dominant phenomena affecting fuel discharge through the CRGT are identified based on parametric calculations by the SIMMER code. Next, validations on the code models closely relating to these phenomena were carried out based on experimental data. It was shown that the SIMMER code with some model modifications could reproduce the experimental results appropriately. Through the present study, the evaluation methodology for the molten-fuel discharge through the CRGT was successfully developed.

关 键 词：Sodium-cooled fast reactor  core disruptive accident molten-fuel discharge  FBR （fast breeder reactor） safety analysis code SIMMER. 

分 类 号：TP309.5[自动化与计算机技术—计算机系统结构] TL433[自动化与计算机技术—计算机科学与技术]