A proposed Regulatory Guide basis for spent fuel decay heat
Conference
·
OSTI ID:5745006
A proposed revision to Regulatory Guide 3.54, Spent Fuel Heat Generation in an Independent Spent Fuel Storage Installation'' has been developed for the US Nuclear Regulatory Commission. The proposed revision includes a data base of decay heat rates calculated as a function of burnup, specific power, cooling time, initial fuel {sup 235}U enrichment and assembly type (i.e., PWR or BWR). Validation of the calculational method was done by comparison with existing measured decay heat rates. Procedures for proper use of the data base, adjustment formulae accounting for effects due to differences in operating history and initial enrichment, and a defensible safety factor were derived. 15 refs., 6 tabs.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- Sponsoring Organization:
- NRC; Nuclear Regulatory Commission, Washington, DC (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5745006
- Report Number(s):
- CONF-910435-79; ON: DE91012504
- Country of Publication:
- United States
- Language:
- English
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COMPUTER CODES
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DATA BASE MANAGEMENT
DOCUMENT TYPES
ENERGY SOURCES
ENRICHED URANIUM REACTORS
FUELS
MANAGEMENT
MATERIALS
NUCLEAR FUELS
O CODES
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POINT BEACH-2 REACTOR
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PWR TYPE REACTORS
REACTOR MATERIALS
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