Calculation of test leakage rate for a spent-fuel cask

Conference · Tue Jan 01 04:00:00 EST 1991 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5763362

Fischer, L E ^[1]

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1. Lawrence Livermore National Lab., CA (United States)

Prior to shipment, a spent-fuel cask must be leak tested to ensure that no radioactive releases greater than regulatory limits will occur during normal transport and accident conditions. In this paper, the authors present a method for estimating the releasable radioactive material from a cask and the associated leak-testing requirements to ensure compliance with 10CFR71 regulations. The authors used the ANSI N14.5 standard to calculate the test-leakage rates from the maximum permissible releases determined from regulations.

• OSTI ID: 5763362
• Report Number(s): CONF-910603--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 63
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
420204* -- Engineering-- Shipping Containers
ACCIDENTS
ACTIVITY LEVELS
CALCULATION METHODS
CASKS
CERTIFICATION
COMPLIANCE
CONTAINERS
EMERGENCY PLANS
ENERGY SOURCES
ENRICHED URANIUM REACTORS
FUEL ASSEMBLIES
FUEL INTEGRITY
FUELS
LEAKS
MATERIALS
MATHEMATICAL MODELS
NUCLEAR FUELS
PERFORMANCE
PERFORMANCE TESTING
POWER REACTORS
PWR TYPE REACTORS
REACTOR MATERIALS
REACTORS
REGULATIONS
SPENT FUEL CASKS
SPENT FUELS
TESTING
THERMAL REACTORS
TRANSPORT
WATER COOLED REACTORS
WATER MODERATED REACTORS