钠冷行波堆TP-1瞬态安全分析  

Transient and Safety Analysis for TP-1 Sodium Cooled TWR

作　　者：韦宏洋 丛腾龙 田文喜[1] 杨江[1] 秋穗正[1] 苏光辉[1] 

机构地区：[1]西安交通大学能源与动力工程学院,陕西西安710049

出　　处：《原子能科学技术》2013年第11期2020-2025,共6页Atomic Energy Science and Technology

基　　金：国家自然科学基金资助项目(91126009);杰出青年基金资助项目(11125522)

摘　　要：钠冷行波堆作为一种具有潜力的新堆型,正处于概念研究阶段。本工作根据TerraPower公司最新设计的钠冷行波堆TP-1的具体结构和运行工况方案,建立其一回路主要部件的物理数学模型,用Fortran语言初步开发了钠冷行波堆瞬态安全分析程序TAST,并对钠冷行波堆稳态进行计算,表明系统程序运行稳定可靠。采用TAST对失流事故和反应性引入事故进行计算,得到关键参数的瞬态变化,初步验证了钠冷行波堆在这两个事故工况下的安全性。As a new conceptual reactor, traveling wave reactor （TWR） is under fundamental research phase. The physical and mathematical models of the main parts of the primary circuit of TP-1 sodium cooled TWR designed by TerrraPower Co. were established, and the transient and safety analysis code TAST for sodium cooled TWR was preliminarily developed with Fortran program. Steady state analysis proves that the stability and dependability of TAST code for TWR are preserved. The variations of main parameters for loss of flow and reactivity insertion accidents were calculates, the results show that TWR is safe under such two transients.

关 键 词：钠冷行波堆 TP-1 失流事故 反应性引入事故 

分 类 号：TL333[核科学技术—核技术及应用]