Severe accidents in spent fuel pools in support of generic safety, Issue 82

Technical Report · Wed Jul 01 00:00:00 EDT 1987

DOI:https://doi.org/10.2172/6135335· OSTI ID:6135335

Sailor, V L; Perkins, K R; Weeks, J R; Connell, H R

This investigation provides an assessment of the likelihood and consequences of a severe accident in a spent fuel storage pool - the complete draining of the pool. Potential mechanisms and conditions for failure of the spent fuel, and the subsequent release of the fission products, are identified. Two older PWR and BWR spent fuel storage pool designs are considered based on a preliminary screening study which tried to identify vulnerabilities. Internal and external events and accidents are assessed. Conditions which could lead to failure of the spent fuel Zircaloy cladding as a result of cladding rupture or as a result of a self-sustaining oxidation reaction are presented. Propagation of a cladding fire to older stored fuel assemblies is evaluated. Spent fuel pool fission product inventory is estimated and the releases and consequences for the various cladding scenarios are provided. Possible preventive or mitigative measures are qualitatively evaluated. The uncertainties in the risk estimate are large, and areas where additional evaluations are needed to reduce uncertainty are identified.

• Research Organization: Brookhaven National Lab. (BNL), Upton, NY (United States); Nuclear Regulatory Commission, Washington, DC (USA). Div. of Reactor and Plant Systems
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 6135335
• Report Number(s): NUREG/CR-4982; BNL-NUREG-52093; ON: TI87013442
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
SPENT FUEL STORAGE
PWR TYPE REACTORS
FUEL POOLS
STORAGE FACILITIES
ACCIDENTS
FAILURES
FISSION PRODUCTS
FUEL CANS
SAFETY
SPENT FUEL ELEMENTS
ZIRCALOY
ALLOYS
FUEL ELEMENTS
ISOTOPES
MATERIALS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTORS
STORAGE
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
050900* - Nuclear Fuels- Transport
Handling
& Storage
220900 - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled