NB/T 20175-2012Technical Specification for Installation and Acceptance of Fuel Handling and Storage System of PWR Nuclear Power Plants (English PDF)
压水堆核电厂燃料操作与贮存系统安装及验收技术规程
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Issued by
NEA
Level / Type
Industry · Recommended
Issue date
October 19, 2012
Implementation date
March 1, 2013
Scope
NB/T 20175-2012 is the English-translated version of 压水堆核电厂燃料操作与贮存系统安装及验收技术规程.
Installation and acceptance of the fuel handling and storage system of a pressurized water reactor plant is governed by NB/T 20175-2012, a recommended Chinese energy industry standard.
It states the general technical requirements for that system, and it applies to the site installation of its equipment and to the acceptance carried out afterwards.
It therefore concerns the erection work on refuelling and fuel storage equipment rather than its design. Published by the National Energy Administration under the Chinese classification F63, it quotes GB/T 16702, NB/T 47015, NB/T 20001, the NB/T 20002 and NB/T 20003 series, NB/T 20133.1 and NB/T 20133.6, and with the HAF 602 and HAF 603 regulations. Issued on 19 October 2012, it has applied since 1 March 2013.
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Document preview — NB/T 20175-2012
National Standard of the People's Republic of China
- ICS
- 27.120.99
Issued by: National Energy Administration of the People's Republic of China
Contents
- 2 Normative references
2 Normative references
NB/T 20175-2012 cites the following standards, which apply in full or in part through the references made to them in its clauses.
GB/T 16702
NB/T 47015
NB/T 20001
NB/T 20002.1
NB/T 20002.2
NB/T 20002.3
NB/T 20002.4
NB/T 20002.6
NB/T 20003.3
NB/T 20003.4
NB/T 20003.7
NB/T 20133.1
NB/T 20133.6
HAF 602
HAF 603
......
This preview omits tables, figures, formulas and parts of the technical clauses. The complete document — 15 pages — is available in the English PDF.
Referenced standards
Normative references
- GB/T 16702Design code for mechanical components in nuclear island of pressurized water reactor nuclear power plants
- NB/T 47015Welding specification for pressure vessels
- NB/T 20001Manufacturing specifications for nuclear island machinery and equipment in pressurized water reactor nuclear power plants
- NB/T 20002.1Welding code for mechanical components of PWR nuclear islands - Part 1: General requirements
- NB/T 20002.2Welding code for nuclear island mechanical equipment of pressurized water reactor nuclear power plant - Part 2: Acceptance of welding filler materials
- NB/T 20002.3Welding code for nuclear island mechanical equipment of pressurized water reactor nuclear power plant - Part 3: Welding procedure qualification
HAF 602 · HAF 603
Similar standards
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Related Standards
GB/T 16702.1-2025 — Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants — Part 1: General principle
GB/T 16702.2-2025 — Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 2: Class 1 components
GB/T 16702-2019 — Design code for mechanical components in nuclear island of pressurized water reactor nuclear power plants
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