摘要
简述了１０ＭＷ研究堆堆芯热工水力设计的准则、设计基础和ＣＴＳＡ程序特点。经ＣＴＳＡ程序计算得：在正常运行、运行暂态和可预期事故工况下，燃料元件表面不会发生偏离泡核沸腾，元件芯块最高温度为１１４．９５℃，小于设计限值４００℃；在稳态额定工况下，堆内不会出现过冷沸腾；堆芯冷却剂平均流速为３．２ｍ／ｓ，小于临界流速；设计满足了有关安全准则要求，并为可预期的事故工况留有足够的安全裕量。
Thermal hydraulic design of reactor core for 10MW research reactor together with accepted criteria and design base is presented in this paper.The main features of CTSA code used for thermal hydraulic design of reactor core are also introduced.The calculation results show that:In normal operation,operation transient and anticipated accident condition,departure from nucleate boiling doesn′t happen on fuel surface,the maximum temperature of fuel pellet is 114.95℃ (lower than 400℃);In steady full power condition,subcooling boiling doesn′t happen in reactor core;The average flowrate of reactor core coolant is 3.2 m/s,lower than the value of critical flowrate;thermal hydraulic design of reactor core for 10MW research reactor is consistent with requirement of safety criteria;enough safety margin is given for anticipated accidents.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
1998年第4期293-296,共4页
Nuclear Power Engineering
关键词
研究堆
热工水力设计
临界热流密度
Research reactor Thermal Hydraulic design Critical heat flux
