From the economy of reactor coolant pump,based on computational fluid dynamics technology the numerical investigation of internal flow in reactor coolant pump of one 300MWe nuclear power plant in China was made.
从反应堆冷却剂泵的经济性出发,以国内某300MW e级核电站主泵为对象,利用计算流体技术(CFD)对其内部流场进行了数值研究,以效率为中心,重点分析了主泵叶轮段、导叶体段的速度、压力分布。
The theoretical and experimental studies of reactor coolant pump accidents encountered nation-wide and world-wide were described.
介绍了国内外反应堆冷却剂泵在发生各种事故情况下的理论及试验研究情况,针对核主泵断电惰转过程中的瞬态水力特性进行了试验研究,对试验结果进行了讨论。
Numerical Simulation of Three-Dimensional Flow Through Full Passage and Performance Prediction of Nuclear Reactor Coolant Pump
核反应堆冷却剂循环泵全流道三维数值模拟及性能预估
a nuclear reactor using gas as a coolant.
用气体做冷却剂的核子反应堆。
reactor coolant leakage calculatio
反应堆冷却剂泄漏计算
Source Terms Calculation Analysis for the Reactor and Primary Coolant System of Qinshan Phase II NPP Project
秦山核电二期工程反应堆及反应堆冷却剂系统源项计算分析
Design of the Reactor and Reactor Coolant System for Qingshan Phase II NPP Project
秦山核电二期工程反应堆及反应堆冷却剂系统设计
reactor coolant system dose equivalent
反应堆冷却剂系统剂量当量
Possessing high technology reactor coolant pump is the pride of a nuclear power plant.
拥有技术上先进的反应堆冷却剂泵,是核电厂的骄傲。
Mechanical Analysis of Reactor Coolant System for Qinshan Phase II NPP Project Main Coolant System and Auxiliary System
秦山核电二期工程反应堆主冷却剂系统与辅助系统力学分析
charging/make-up flow [reactor coolant system]
上充／补给水流量〔反应堆冷却剂系统〕
reactor coolant circuit integrity
反应堆冷却剂回路完整性
reactor building cooling unit
反应堆建筑物冷却装置
granular graphite cooled reactor
颗粒状石墨冷却反应堆
liquid metal cooled reactor
液态金属冷却反应堆
light water cooled heavy water reactor
轻水冷却重水反应堆
primary reactor coolant system
反应堆一次冷却系统
graphite moderated sodium cooled reactor
石墨慢化钠冷却反应堆
BGR (Bismuth-Graphite Reactor)
石墨慢化铋冷却反应堆
SCHWR (Steam-Cooled Heavy Water Reactor)
蒸汽冷却式重水反应堆