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ANS 54.1 : 1989

Superseded

Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

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superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

GENERAL SAFETY DESIGN CRITERIA FOR A LIQUID METAL REACTOR NUCLEAR POWER PLANT

Available format(s)

Hardcopy , PDF

Superseded date

08-21-2023

Language(s)

English

Published date

01-12-2013

Establishes General Safety Design Criteria which constitute the minimum safety requirements for liquid metal reactor (LMR) nuclear power plants and are intended to be used for the design of LMRs in lieu of the General Design Criteria of Nuclear Power Plants in the CFR 10 part 50. These criteria are intended to be applicable to LMR designs which use various arrangements of components, such as those characterized as loop designs, pool designs or combinations thereof. These reactors use sodium in the reactor coolant system and operate with a fast (high energy) neutron spectrum.

Committee
ANS
DocumentType
Standard
Pages
28
PublisherName
American Nuclear Society
Status
Superseded
SupersededBy

ANS 53.1 : 2011(R2016) NUCLEAR SAFETY DESIGN PROCESS FOR MODULAR HELIUM-COOLED REACTOR PLANTS

IEEE 379-2014 IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems
ANS 58.9 : 2002(R2015) SINGLE FAILURE CRITERIA FOR LWR SAFETY-RELATED FLUID SYSTEMS
ASME NQA 1 : 2015 Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015)

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US$119.00
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