反应堆安全分析英文缩写

ABWR

advanced boiling water reactor

先进沸水堆

APWR

advanced pressurized water reactor

先进压水堆

AP

advance passive plant

先进非能动电厂

ADS

accelerator driven system

加速器驱动机构

AFP

auxiliary feedwater pump

辅助给水泵

ATWS

anticipated transient without screen

未能停堆的预计瞬变

ANSI

American national standards Institute

美国标准协会

BDBA

beyond design basic accident

超设计基准事故

BOL

beginning of life

寿期初

CEFR

china experimental fast reactor

中国实验快堆

CSS

containment spray system

安全壳喷淋系统

CVCS

chemical and volume control system

化容控制系统

CSRDM

control and safety rod drive mechanism

控制棒安全棒驱动机构

CHF

critical heat flux

临界热流密度

DHX

direct heat exchanger

直接热交换器

DBA

design basic accident

设计基准事故

DOE

department of energy

美国能源部

DCH

direct containment heating

直接安全壳加热

DNBR

departure from nuclear boiling ratio

偏离泡核沸腾比

ESD

emergency shutdown device

紧急停堆仪器

ECCS

emergency core cooling system

应急堆芯冷却系统

EPR

European pressurized reactor

欧洲压水堆

ESS

emergency shutdown system

紧急停堆系统

EFS

emergency feedwater system

应急给水系统

ESF

emergency safety features

专设安全设施

EPRI

the electric power research institute

美国电力研究会

EOL

end of life

寿期末

EFPD

effective full power days

有效满功率天数

EM

evaluation model

评价模型

EFW

emergency feed water

紧急供水

GFR

gas-cooled fast reactor

气冷快堆

HEM

homogeneous equilibrium model

均相平衡模型

HPIS

high pressure injection system

高温安注系统

HTGR

high- temperature gas-cooled reactor

高温气冷堆

HTTR

high-temperature test reactor

高温工程试验堆

IFR

integral fast reactor

整体快堆

IHX

integral heat exchanger

中间热交换器

INSAG

International nuclear safety

国际核安全咨询

IDCOR

industry degraded core rule making

工业退役堆芯规则

LFR

lead-cooled fast reactor

铅冷快堆

LPIS

low pressure injection system

低压安注系统

LOCA

loss of coolant accident

失水事故

LOFA

loss of flow accident

失流事故

LOFW

loss of boilen feed water

丧失蒸汽发生器给水