Standard No.:	NB/T 20057.2-2012
English Name:	Pressurized Water Reactor Nuclear Power Plants Reactor System Design - Core- Part 2: Thermal Hydraulic Design Criteria
Chinese Name:	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
Professional Classification:	NB    Professional Standard - Energy
Source Content Issued by:	National Energy Administration
Issued on:	2012-1-6
Implemented on:	2012-4-6
Status:	valid
Superseding:	EJ/T 319-1992
Target Language:	English
File Format:	PDF
Word Count:	6000 words
Translation Price(USD):	180.0
Delivery:	via email in 1 business day

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

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