NB/T 20403-2017 Active Industry standards-Energy

NB/T 20403-2017 The transient analysis of pressure and temperature in the compartment of a pressurized water reactor nuclear power plant

Publish Date: 2017-02-10 Implement Date: 2017-07-01 For services related to genuine standard inquiry, procurement, translation, and other related services in China, please Contact Us

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Basic Information

Standard Code: NB/T 20403-2017

Standard Type: Industry standards

Standard Status: Active

is_force_gb: no

CCS Name: \nNuclear island of a nuclear power plant

ICS Name: Nuclear power stations, safety

Publish Date: 2017-02-10

Implement Date: 2017-07-01

Pages: 32 pages

Scope

This standard specifies the methods and guidelines necessary for analyzing the short-term and long-term pressure and temperature transients and flooding effects within and outside the containment of pressurized water reactors caused by high-energy or medium-energy pipe ruptures or other events. This standard applies to the design review of containment and equipment support within and outside the containment of pressurized water reactors, and can provide reference for determining the environmental conditions for equipment qualification. This standard does not consider the ejection force caused by pipe ruptures and related effects, nor does it include pipe support design and the determination of the rupture location.