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NB/T 20057.2-2012Pressurized Water Reactor Nuclear Power Plants Reactor System Design - Core - Part 2: Thermal Hydraulic Design Criteria (English PDF)

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

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Issued by

NEA

Level / Type

Industry · Recommended

Issue date

January 6, 2012

Implementation date

April 6, 2012

Scope

NB/T 20057.2-2012 is the English-translated version of 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.

NB/T 20057.2-2012 is the Chinese standard "Pressurized Water Reactor Nuclear Power Plants Reactor System Design - Core - Part 2: Thermal Hydraulic Design Criteria".

Its scope clause reads: This part specifies general principles of thermal hydraulic design for reactors of pressurized water reactor nuclear power plants, thermal hydraulic design criteria of core and principles of determining the design limits of thermal hydraulic parameters.

This part is applicable to thermal hydraulic design of pressurized water reactor nuclear power plants reactors, and can also be used as a reference for thermal hydraulic design of pressurized water reactors (PWRs) for other purposes. Its clauses include terms and definitions; general design principles.

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Document preview — NB/T 20057.2-2012

National Standard of the People's Republic of China

ICS
27.120.20
Replacing
EJ/T 319-1992

Issued by: National Energy Administration of the People's Republic of China

Contents

  • Foreword i
  • 1 Scope
  • 2 Normative references
  • 3 Terms and definitions
  • 4 General design principles
  • 5 Design criteria
  • 6 Principles for determining design limits of thermal hydraulic parameters

1 Scope

This part specifies general principles of thermal hydraulic design for reactors of pressurized water reactor nuclear power plants, thermal hydraulic design criteria of core and principles of determining the design limits of thermal hydraulic parameters.

This part is applicable to thermal hydraulic design of pressurized water reactor nuclear power plants reactors, and can also be used as a reference for thermal hydraulic design of pressurized water reactors (PWRs) for other purposes.

2 Normative references

The following referenced documents are indispensable for the application of this document. For dated references, only the edition cited applies. For undated references, the latest edition of the referenced document (including any amendments) applies.

GB/T 4960 Glossary of nuclear science and technology terms

NB/T 20035-2011 Categorization of conditions of PWR nuclear power plants

NB/T 20103-2012 Accident analysis and safety criteria for pressurized water reactor nuclear power plant

3 Terms and definitions

For the purposes of this document, the terms and definitions given in GB/T 4960 and NB/T 20035-2011 and the following apply.

3.1 best estimate flow

most probable flow under the actual operating conditions of power plant, which does not consider the uncertainty of system flow resistance or pump head, and is determined based on the best estimation of flow resistance of reactor pressure vessels, steam generators and pipelines, and of reactor coolant pump head and flow

3.2 thermal design flow

conservative small flow for the design of thermal performance of reactor core and steam generator, and of main parameters of power plant

3.3 mechanical design flow

conservative large flow for mechanical design of internals and fuel assemblies in reactor pressure vessels

4 General design principles

......
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

Similar standards

Editions of NB/T 20057.2

EditionTitleRevisionStatus
NB/T 20057.2-2012Pressurized Water Reactor Nuclear Power Plants Reactor System Design - Core - Part 2: Thermal Hydraulic Design Criteriacurrent editionCurrent
EJ/T 319-1992Pressurized Water Reactor Nuclear Power Plants Reactor System Design - Core - Part 2: Thermal Hydraulic Design Criteriaprevious editionSuperseded

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