ANS 57.10 : 1996(R2006)

Name: ANS 57.10 : 1996(R2006)
Brand: ANS

Superseded

DESIGN CRITERIA FOR CONSOLIDATION OF LWR SPENT FUEL

Superseded date

29-01-2017

Published date

12-01-2013

Publisher

American Nuclear Society

Provides design criteria for the process of consolidating light water reactor spent nuclear fuel in either a wet or dry environment.

ANS 57.7 : 88(R1997)	DESIGN CRITERIA FOR AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION (WATER POOL TYPE)
ANS 57.8 : 1995(R2017)	FUEL ASSEMBLY IDENTIFICATION

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ANS 51.1 : 83(R1988)	NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS
ANS 52.1 : 83(R1988)	NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS
ANS 57.2 : 1983	LIGHT WATER REACTOR SPENT FUEL STORAGE FACILITIES, REQUIREMENTS FOR,
ANS 8.17 : 2004(R2014)	CRITICALITY SAFETY CRITERIA FOR THE HANDLING, STORAGE AND TRANSPORTATION OF LWR FUEL OUTSIDE REACTORS
ANS 57.1 : 1992(R2015)	DESIGN REQUIREMENTS FOR LIGHT WATER REACTOR FUEL HANDLING SYSTEMS
AISC N690 : 2015	SPECIFICATION FOR SAFETY-RELATED STEEL STRUCTURES FOR NUCLEAR FACILITIES
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ASME NQA 1 : 2015	Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015)
ANS 57.9 : 1992(R2000)	DESIGN CRITERIA FOR AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION (DRY TYPE)
AISC S326 : 1978	SPECIFICATION FOR THE DESIGN, FABRICATION AND ERECTION OF STRUCTURAL STEEL FOR BUILDINGS (WITH COMMENTARY)

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