ANS 54.1-1989
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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GENERAL SAFETY DESIGN CRITERIA FOR A LIQUID METAL REACTOR NUCLEAR POWER PLANT
Hardcopy , PDF
21-08-2023
English
12-01-2013
Important note : Users cannot be edited or removed once added to your Multi user PDF.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
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| PublisherName |
American Nuclear Society
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| Status |
Superseded
|
| SupersededBy |
| 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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