压水堆核电厂反应堆冷却剂丧失事故分析要求
Analysis demand for loss-of-coolant accident of pressurized water reactor nuclear power plants
2012-01-06
NB/T 20187-2012
压水堆核电厂反应堆冷却剂系统设计准则
Design criteria for reactor coolant system in pressurized water reactor nuclear power plants
2012-10-19
EJ/T 1033-1996
压水堆核电厂反应堆容器防止快速断裂评定准则
Assessment criteria for preventing fast rupture of reactor pressure vessel of pressurized water reactor nuclear power plants
1996-10-24
NB/T 20032-2010
压水堆核电厂反应堆压力容器承压热冲击评定准则
Evaluation rule of pressurized thermal schock for reactor pressure vessel of PWR NPP
2010-05-24
NB/T 20444-2017
压水堆核电厂设计基准事故源项分析准则
Analysis criterion of the design basis accident source terms for pressurized water reactor nuclear power plant
2017-04-01
NB/T 20444-2017RK
压水堆核电厂设计基准事故源项分析准则
NB/T 20440-2017
压水堆核电厂反应堆压力容器防止快速断裂评定准则
Assessment criteria for proventing fast rupture of reactor pressure vessel of pressurized water reactor nuclear power plants
2017-04-01
NB/T 20576-2019
压水堆核电厂反应堆压力容器中子注量率分析
NB/T 20688-2023
压水堆核电厂反应堆冷却剂系统设计瞬态分析要求
2023-10-11
NB/T 20439-2017
压水堆核电厂反应堆压力容器压力-温度限值曲线制定准则
Evaluation rule of pressure-temperature limit curves for reactor pressure vessel of pressurized water reactor nuclear-power plants
2017-04-01
NB/T 20372-2016
压水堆核电厂反应堆控制棒驱动机构安装技术规程
Technical regulation for installation of control rod drive mechanism in PWR nuclear power plant
2016-02-05
ISO 23466-2020
Design criteria for the thermal insulation of reactor coolant system main equipments and piping of PWR nuclear power plants
压水堆核电厂反应堆冷却剂系统主要设备和管道绝热设计准则
2020-10-22
NB/T 20057.2-2012
压水堆核电厂反应堆系统设计 堆芯 第2部分：热工水力设计准则
Pressurized water reactor nuclear power plants reactor system design-Core-part 2:Thermal hydraulic design criteria
2012-01-06
GB/T 45569-2025
压水堆核电厂反应堆冷却剂系统设备和管道保温层设计准则
Design criteria for the thermal insulation of reactor coolant system main equipments and piping of PWR nuclear power plants
2025-04-25
EJ/T 918-1994
压水堆核电厂反应堆压力容器压力-温度限值曲线制定准则水中锰-54的分析方法
1994-11-11
NB/T 20100-2016RK
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
NB/T 20334-2015
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 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