1) Loss of coolant accident
失水事故
1.
Loss of coolant accident is considered as design basis accident in the design of nuclear power plant.
失水事故是核电站设计的基准事故之一,是压水堆事故分析关注的重点。
2.
The momentum integral method is applied in the frame of safety analysis of pressure water reactors under hypothetical loss of coolant accident(LOCA) conditions to simulate numerically film condensation, rewetting and vaporization on the inner surface of a pressure water reactor containment.
采用动量积分方法分析压水堆发生失水事故时在安全壳的内表面上的液膜凝结、再浸润和蒸发过程。
3.
To evaluate the safety characteristics of pulsed reactor under LOCA (loss of coolant accident), an analytical model of LOCA is developed and an advanced code XPRLOCA with friendly interactive interface and real time simulation function is coded for simulating LOCA.
针对脉冲反应堆的特点 ,建立了脉冲反应堆失水事故的数学模型 ,编制了脉冲堆失水事故仿真分析软件XPRLOCA。
2) LOCA
['ləukə]
失水事故
1.
PWR LOCA Analysis with Condensation Reflux Model;
采用冷凝回流模型的压水堆失水事故分析
2.
Simulation of LOCA in the auxiliary primary loop system of nuclear power plant;
核动力装置一回路辅助系统失水事故的仿真研究
3.
Realistic Analysis of Intermediate and Small LOCA;
中小破口失水事故现实估算分析
3) Non-LOCA accident
非失水事故
4) emergency cooling period
(失水事故)事故冷却阶段
5) large break loss of coolant accident
大破口失水事故
1.
2 and taking US Westinghouse corporation Surry nuclear power plant as the reference object, a typical three-loop pressurized water reactor severe accident calculation model was established and 25cm large break loss of coolant accident(LBLOCA)in cold and hot leg of primary loop induced core melt accident was analyzed.
2,以美国西屋公司Surry核电站为参考对象,建立了1个典型的3环路压水堆核电站的严重事故分析模型,分别对主回路冷段和热段发生25cm大破口失水事故(LBLOCA)导致的堆芯熔化事故进行研究分析。
2.
The analysis of large break loss of coolant accident(LBLOCA) which occured at nominal power of nuclear power plant is given.
针对核电站额定运行工况下发生冷段大破口失水事故进行了分析。
3.
The characteristics of large break loss of coolant accident(LOCA) for Xi\'an Pulsed Reactor were analyzed.
分析了西安脉冲堆大破口失水事故的特点,建立了适用的数学模型,编制了计算程序。
6) seismic and LOCA conditions
地震和失水事故
1.
Research on reactor dynamic analysis under seismic and LOCA conditions has been fulfilled.
对核反应堆在地震和失水事故下结构动力分析开展了研究,包括反应堆和蒸汽发生器在失水事故下的瞬态卸压载荷分析研究、反应堆结构动力响应分析研究和燃料组件动力响应分析评定研究。
补充资料：N-乙基失水苹果酰亚胺
CAS: 128-53-0
分子式: C6H7NO2
分子量: 125.12
沸点: 210℃
熔点: 41-45℃
中文名称: N-乙基顺丁烯二酰亚胺；1-乙基-1H-吡咯-2,5-二酮；N-乙基失水苹果酰亚胺；N-乙基马来酰亚胺
英文名称: N-Ethyl maleimide；5-dione, 1-ethyl-1H-Pyrrole-2；1-ethyl-1h-pyrrole-5-dione；ethylmaleimide；maleic acid n-ethylimide；n-ethyl-maleimid；n-ethylmaleimide；usaf b-121；ethvlmaleimide；n-ethvlmaleimide
分子式: C6H7NO2
分子量: 125.12
沸点: 210℃
熔点: 41-45℃
中文名称: N-乙基顺丁烯二酰亚胺；1-乙基-1H-吡咯-2,5-二酮；N-乙基失水苹果酰亚胺；N-乙基马来酰亚胺
英文名称: N-Ethyl maleimide；5-dione, 1-ethyl-1H-Pyrrole-2；1-ethyl-1h-pyrrole-5-dione；ethylmaleimide；maleic acid n-ethylimide；n-ethyl-maleimid；n-ethylmaleimide；usaf b-121；ethvlmaleimide；n-ethvlmaleimide
说明：补充资料仅用于学习参考，请勿用于其它任何用途。
参考词条