压水堆核电厂反应堆及一回路噪声分析一般要求
General requirements for noise analysis of reactor and primary loop in pressurized water reactor nuclear power plant
2015-04-02
NB/T 20241-2013
压水堆蒸汽发生器传热管在役检查要求
The requirement of in-service inspection for pressurized water reactor steam
generator tubes
2013-06-08
GOST 24722-1981
Реакторы ядерные энергетические корпусные с водой под давлением (ВВЭР). Общие технические требования
核动力容器封装的加压水反应堆 一般要求
GB/T 40860-2021
压水堆核电厂设计扩展工况分析要求
Analysis requirements for design extension conditions of pressurized water reactor nuclear power plants
2021-10-11
GOST 26635-1985
Реакторы ядерные энергетические корпусные с водой под давлением. Общие требования к системе внутриреакторного контроля
核动力容器封装的加压水反应堆 核心反应堆监测系统的一般要求
NB/T 20100-2016
压水堆核电厂反应堆冷却剂系统和主蒸汽系统超压分析要求
Requirements of overpressure analysis for reactor coolant system and main steam system for pressurized water reactor nuclear power plants
2016-02-05
NB/T 20104-2012
压水堆核电厂未能紧急停堆的预期瞬态分析要求
Analysis requirement for anticipated transient without scram on Pressurized water reactor nuclear power plants
2012-01-06
NB/T 20309-2014
能动安全系统压水堆核电厂总设计要求
General design requirements of pressurized water reactor nuclear power plants with active safety systems
2014-06-29
NB/T 20192-2012
压水堆核电厂先导式安全阀通用要求
General requirements for pilot operated safety valves of pressurized water reactor nuclear power plant
2012-10-19
GOST 24693-1981
Реакторы ядерные энергетические корпусные с водой под давлением. Общие требования к системе борного регулирования
核动力容器封装的水压反应堆 对普通规则的普遍规律
GB/T 35730-2017
非能动安全系统压水堆核电厂总设计要求
General design requirements of pressurized water reactor nuclear power plants with passive safety systems
2017-12-29
GB/T 41090-2021
能动安全系统压水堆核电厂总设计要求
General design requirements of pressurized water reactor nuclear power plants with active safety systems
2021-12-31
NB/T 20133.1-2012
压水堆核电厂设施设备防护涂层规范 第1部分:通用要求
Specifications for protective coatings used in pressurized water reactor nuclear power plants-Part 1:General requirements
2012-01-06
GOST 24789-1981
Каналы измерительные системы внутриреакторного контроля ядерных энергетических корпусных реакторов с водой под давлением. Общие технические требования
核心仪表系统检测器组件的nyclear动力容器封装的加压水反应堆 一般技术要求
NB/T 20560.3-2021
压水堆核电厂应急堆芯冷却系统过滤器设计和性能评价 第3部分:上游分析技术要求
Design and performance evaluation of emergency core cooling stainer for pressurized water reactors nuclear power plants—Part 3: Technical requirements for upstream effects analysis