Code of China Chinese Classification Professional Classification ICS Classification Latest Value-added Services

Title Standard No. Implemented On
Code for fire protection design of nuclear power plantGB/T 22158-20212022-5-1
Design code for mechanical components in nuclear island of pressurized water reactor nuclear power plantsGB/T 16702-20192020-7-1
Electrical penetration assemblies in containment structures for nuclear power plantsGB/T 13538-20172018-7-1
Nuclear Power Plants - Instrumentation Important to Safety - Radiation Monitoring for Accident and Post-accident Conditions - Part 1: General RequirementsGB/T 12726.1-20132014-8-1
Nuclear power plants—Instrumentation important to safety—Radiation monitoring for accident and post-accident conditions—Part 4:Equipment for continuous in-line or on-line monitoring of radioactivity in process streamsGB/T 12726.4-20132014-8-1
Nuclear power plants―Instrumentation important to safety―Radiation monitoring for accident and post-accident conditions―Part 2:Equipment for continuous off-line monitoring of radioactivity in gaseous effluents and ventilation airGB/T 12726.2-20132014-8-1
Classification for the items of pressurized water reactor nuclear power pantsGB/T 17569-20132013-7-1
Management requirement of ageing of instrumentation and control systems important to safety for nuclear power plantsGB/T 29308-20122013-6-1
Technical code for engineering surveying of nuclear power station GB 50633-20102011-10-1
Qualification of electrical penetration assemblies in containment structures for nuclear power plantsGB/T 25837-20102011-9-1
Technical guideline of valves commissioning for nuclear power plantGB/T 25739-20102011-5-1
Design Standard of Fire Protection in Nuclear Power PlantGB/T 22158-20082009-4-1
General safety principles of unclear reactor protection systemGB/T 4083-20052006-3-1
Fire protection Criteria for Nuclear Power PlantsEJ/T 1082-20052005-7-1
Classification for the Items of Pressurized Water Reactor Nuclear Power PlantsGB/T 17569-19981999-7-1
Design rules for mechanical components of PWR nuclear islandsGB/T 16702-19961997-1-2
Pressureized water reactor pressure vessel - The principle of selecting materials and the basic requirements of the materialsGB/T 15443-19951995-10-1
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