简化沸水堆(SSBWR-200)的热工设计和事故分析

Thermal hydraulic design and accident analysis of small simplified BWR (SSBWR- 200)

设计开发了新一代小型先进简化沸水堆— SSBWR-2 0 0。采用全功率自然循环、较低的功率密度、堆芯以上更大的冷却剂装量、新型的水力学控制棒传动系统、非能动余热载出系统以及取消堆芯紧急冷却系统、安全壳冷却及喷淋系统等先进设计。通过引入反应性扰动以及对 6种典型事故的计算分析 ,结果表明 :SSBWR- 2 0 0具有良好的稳定性和安全性 ,可以应用于热电联供、区域供热。

The SSBWR 200, developed by the Institute of Nuclear Energy Technology (INET) of Tsinghua University based on the nuclear heating reactor (NHR) technology, is a new kind of small simplified BWR. The system uses natural circulation, lower power density, larger coolant capacity, and a passive residual heat removal system to eliminate the emergency core cooling system (ECCS) and the containment cooling and spray system (CCS&CSS), so that the resulting simplified system is very safe and can be used in many fields such as co generation, district heating, seawater desalination, etc. SSBWR 200 has been proven to be stable and safe by the analysis of reactivity disturbance and six typical accidents.