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压水堆慢化剂反应温度系数的计算与测量

Calculation and Measurement of the Moderator Temperature Coefficient of Reactivity for Pressurized Water Reactors

压水堆辅助给水系统

Auxiliary Feedwater System for Pressurized Water Reactors

轻水反应堆核燃料衰变功率的计算 第2部分：压水反应堆用混合铀钚氧化物(MOX)核燃料

Calculation of the decay power in nuclear fuels of light water reactors - Part 2: Mixed-uranium-plutonium oxide (MOX) nuclear fuel for pressurized water reactors

核电站 加压轻水反应堆

Nuclear power plants - Pressurized light water reactors

压水堆棒束型燃料组件辐照后检查 第13部分：燃料棒X射线美利体育登录入口官网

Post-Irradiation Inspection of PWR Bundle Fuel Assemblies Part 13: X-ray Examination of Fuel Rods

压水堆棒束型燃料组件辐照后检查 第16部分：燃料棒内压测量

Post-irradiation inspection of pressurized water reactor bundle fuel assemblies-Part 16: Internal pressure measurement of fuel rods

压水堆棒束型燃料组件辐照后检查 第19部分：燃料包壳管拉伸试验

Post-irradiation inspection of fuel assemblies of pressurized water reactor bundle type - Part 19: Fuel cladding tube tensile test

压水堆噪声分析一般要求

General Requirements for PWR Noise Analysis

核燃料组件制造中的质量保证

Quality assurance for nuclear fuel assembly fabrication

监督压水堆堆芯充分冷却的测量要求.第2部分:冷停堆期间监测仪表的要求

Measurements for monitoring adequate cooling within the core of pressurized light water reactors - Part 2: Instrumentation requirements during cold shutdown

潜艇核动力装置设计安全规定 第20部分：压水堆堆内构件设计准则

Safety regulations for the design of submarine nuclear power plants Part 20: Design criteria for pressurized water reactor internals

潜艇核动力装置设计安全规定 第9 部分：压水堆结构总体设计准则

Safety regulations for the design of submarine nuclear power plants Part 9: Overall design criteria for pressurized water reactor structures

水缓水冷动力反应堆.中子物性值计算的一般要求

Water-moderated water-cooled power reactors. General requirements to performing of neutron physical calculations

核电厂 仪表系统 压水轻水堆堆芯充分冷却监测测量

Nuclear power plants - Instrumentation systems - Measurements for monitoring adequate cooling within the core of pressurized light water reactors

核电站—仪表系统—监测压水堆反应堆内充分冷却的测量

Nuclear power plants - Instrumentation systems - Measurements for monitoring adequate cooling within the core of pressurized light water reactors

核反应堆仪表 加压轻水反应堆 (PWR) 冷停堆期间监测堆芯的正确冷却（1.0 版）

Nuclear Reactor Instrumentation - Pressurized Light Water Reactors (PWR) - Monitoring Adequate Cooling within the Core During Cold Shutdown (Edition 1.0)

压水堆核电厂核蒸汽供应系统热平衡试验

Thermal balance test of nuclear steam supply system of pressurized water reactor nuclear power plant

压水堆核电厂反应堆系统设计.堆芯.第1部分：核设计

Pressurized water reactor nuclear power plants reactor system design.Core.Part 1: Nuclear design

压水堆核电厂蒸汽发生器设计制造规范

Design and fabrication specification for steam generator of pressurized water reactor nuclear power plants

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

核电厂二回路系统冲洗导则

Guidelines for Flushing Secondary Circuit System of Nuclear Power Plant

压水反应堆重新加载启动物理试验（ISO 18077:2018 IDT）

Reload startup physics tests for pressurized water reactors (ISO 18077:2018, IDT)