Calculation of test leakage rate for a spent fuel cask

Conference · Tue Jan 01 04:00:00 EST 1991

OSTI ID:5789073

Fischer, L E

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 we present a method for estimating the releasable radioactive material from a cask and the associated leak-testing requirements to ensure compliance with 10 CFR 71 regulations. We used the ANSI N14.5 standard to calculate the test-leakage rates from the maximum permissible releases determined from regulations.

• Research Organization: Lawrence Livermore National Lab., CA (United States)
• Sponsoring Organization: DOE; USDOE, Washington, DC (United States)
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 5789073
• Report Number(s): UCRL-JC-106203; CONF-910603--26; ON: DE92009464
• Country of Publication: United States
• Language: English

Related Subjects

050900* -- Nuclear Fuels-- Transport
Handling
& Storage
054000 -- Nuclear Fuels-- Health & Safety
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CASKS
COBALT 60
COBALT ISOTOPES
CONTAINERS
FISSION PRODUCT RELEASE
FUEL ELEMENTS
FUEL RODS
INTERMEDIATE MASS NUCLEI
INTERNAL CONVERSION RADIOISOTOPES
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
LEAK TESTING
MANAGEMENT
MATERIALS
MINUTES LIVING RADIOISOTOPES
NUCLEI
ODD-ODD NUCLEI
RADIOACTIVE EFFLUENTS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
RADIOISOTOPES
REACTOR COMPONENTS
REGULATIONS
RELEASE LIMITS
SAFETY ANALYSIS
SPENT FUEL CASKS
TESTING
TRANSPORT
WASTE MANAGEMENT
WASTE TRANSPORTATION
WASTES
YEARS LIVING RADIOISOT