基于RELAP5的双功能液态锂铅实验包层模块安全分析  

Safety Analysis on Dual-functional Lithium Lead Test Blanket Module With RELAP5

作　　者：李伟[1] 田文喜[1] 秋穗正[1] 苏光辉[1] 

机构地区：[1]西安交通大学动力工程多相流国家重点实验室核科学与技术系,陕西西安710049

出　　处：《原子能科学技术》2013年第11期2046-2052,共7页Atomic Energy Science and Technology

基　　金：ITER计划专项课题资助项目(2009GB109001)

摘　　要：利用嵌入了液态锂铅(LiPb)的热工水力子模块的系统程序RELAP5/MOD3,对双功能液态锂铅(DFLL)实验包层模块(TBM)的安全特性进行评价。对DFLL-TBM及其辅助冷却系统的稳态运行工况、预期运行事件和相关事故工况进行了建模、计算和分析。计算结果表明,稳态运行时第一壁(FW)结构材料表面最高温度低于允许值550℃。事故工况下氦气泄漏引起的ITER真空室(VV)、窗口设备室(port cell)以及托卡马克冷却水系统大厅拱顶(TCWS vault)的增压均低于ITER要求的限值0.2MPa。实验包层钢结构不会熔化且可通过辐射换热有效地导出衰变余热。DFLL-TBM的设计可满足ITER对其热工水力安全方面的要求。Safety assessment on the dual-functional lithium lead test blanket module （DFLL-TBM） was performed wiich a modified version of RELAPS/MOD3 code in which the LiPb eutectic thermal-hydraulic sub-module was inserted. The DFLL-TBM and its ancillary cooling systems were modeled to conduct the computation and analysis for steady-state operation, anticipated operational incidents and relevant accidents. tational results indicate that the maximum surface temperature of the first wa Compu- 1 （FW） structural material is lower than the allowable value of 550 ℃. For the accident analy-ses, none of the pressure increases in ITER vacuum vessel （VV）, port cell and TCWS vault induced by helium leaking is beyond the ITER safety limit of 0.2 MPa. No melting of the TBM box is found and the decay heat can be removed efficiently by the radiationheat transfer. With the current design, DFLL-TBM can meet the thermal-hydraulic safety requirements from ITER.

关 键 词：RELAP5 液态锂铅 实验包层模块 事故工况 

分 类 号：TL69[核科学技术—核技术及应用]