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Engineering approach to criticality safety analysis in an irradiated fuel cask

Journal Article · · Trans. Amer. Nucl. Soc., v. 17, p. 277
OSTI ID:4401743
;
From joint meeting of the American Nuclear Society and the Atomic Industrial Forum and Nuclear Energy Exhibition; San Francisco, California, USA (11 Nov 1973). See CONF-731101-.
Research Organization:
Nuclear Assurance Corp., Atlanta
NSA Number:
NSA-29-005657
OSTI ID:
4401743
Journal Information:
Trans. Amer. Nucl. Soc., v. 17, p. 277, Journal Name: Trans. Amer. Nucl. Soc., v. 17, p. 277; ISSN TANSA
Country of Publication:
Country unknown/Code not available
Language:
English

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Related Subjects

*BWR TYPE REACTORS-- SPENT FUEL ELEMENTS
*CASKS-- SAFETY
*CRITICALITY-- SPENT FUEL ELEMENTS
*SPENT FUEL ELEMENTS-- TRANSPORT
FUEL ASSEMBLIES
K CODES
L CODES
N52420* --Nuclear Materials & Waste Management-- Transportation--Containers