现行

GOST R 59430-2021

Устройства внутрикорпусные водо-водяного энергетического реактора. Расчет на прочность на постпроектных стадиях
水动力反应堆压力容器内件 设计后阶段的强度分析

现行

NB/T 20407-2017

压水堆核电厂堆内构件设计制造规范
Specification for design and fabrication of reactor vessel internals in pressurized water reactor nuclear power plants

2017-02-10

现行

EJ/T 474-2000

压水堆核电厂反应堆压力容器金属保温层技术条件
Specification for reactor pressure vessel metal insulation for pressurized water reactor nuclear power plants

2001-02-28

现行

GOST R 59115.14-2021

Обоснование прочности оборудования и трубопроводов атомных энергетических установок. Расчет на сопротивление хрупкому разрушению корпуса водо-водяного энергетического реактора
核电装置设备和管道的强度评估规则 压水堆容器的强度评定

现行

EJ/T 321-1998

压水堆核电厂堆内构件设计准则
Design criterion of reactor internals for pressurized water reactor nuclear power plants

1998-10-13

现行

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

现行

NB/T 20008.25-2015

压水堆核电厂用其他材料 第25部分：堆内构件用GH4169合金丝
Other material for pressurized water reactor nuclear power plants Part 25:GH4169 alloy wires for reactor vessel internals

2015-07-01

现行

NB/T 20008.24-2015

压水堆核电厂用其他材料 第24部分：堆内构件用GH4145合金棒
Other material for pressurized water reactor nuclear power plants Part 24:GH4145 alloy bars for reactor vessel internals

2015-07-01

现行

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

现行

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

现行

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

现行

GB/T 16702.6-2025

压水堆核电厂核岛机械设备设计规范 第6部分：堆内构件
Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants—Part 6: Reactor vessel internals

2025-02-28

现行

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

现行

NB/T 20007.42-2015

压水堆核电厂用不锈钢 第42部分：堆内构件用沉淀硬化不锈钢棒
Stainless steel for pressurized water reactor nuclear power plants Part 42:precipitation-hardening stainless steel bars for reactor vessel internals

2015-07-01

现行

NB/T 20007.40-2015

压水堆核电厂用不锈钢 第40部分：堆内构件用奥氏体不锈钢锻件
Stainless steel for pressurized water reactor nuclear power plants-Part 40:austenitic stainless steel forgings used for reactor vessel internals

2015-07-01

现行

IEC 61502-1999

Nuclear power plants - Pressurized water reactors - Vibration monitoring of internal structures
核电站 - 加压水反应堆 - 内部结构的振动监测

1999-11-04

现行

NB/T 20382-2016

压水堆核电厂堆内构件的振动监测
Vibration monitoring of internal structures in pressurized water reactor nuclear power plants

2016-02-05

现行

NB/T 20431-2017

压水堆核电厂钢制安全壳结构整体性试验
Structural integrity test of steel containment vessel for pressurized water reactor power plants

2017-04-01

现行

NB/T 20007.41-2015

压水堆核电厂用不锈钢 第41部分：堆内构件用奥氏体不锈钢无缝钢管
Stainless steel for pressurized water reactor nuclear power plants Part 41:austenitic stainless steel seamless pipes used for reactor vessel internals

2015-07-01

现行

GB/T 42143-2022

压水堆核电厂钢制安全壳设计建造规范
Specification for design and construction of steel containment vessel of pressurized water reactor nuclear power plant

2022-12-30