Fission gas and iodine release measured in IFA-430 up to 15 GWd/t UO/sub 2/ burnup. [PWR; BWR]

Conference · Sat Jan 01 00:00:00 EST 1983

OSTI ID:6062827

Appelhans, A D; Turnbull, J A; White, R J

The release of fission products from fuel pellets to the fuel-cladding gap is dependent on the fuel temperature, the power (fission rate) and the burnup (fuel structure). As part of the US Nuclear Regulatory Commission's Fuel Behavior Program, EG and G Idaho, Inc., is conducting fission product release studies in the Heavy Boiling Water Reactor in Halden, Norway. This paper presents a summary of the results up to December, 1982. The data cover fuel centerline temperatures ranging from 700 to 1500/sup 0/C for average linear heat ratings of 16 to 35 kW/m. The measurements have been performed for the period between 4.2 and 14.8 GWd/t UO/sub 2/ of burnup of the Instrumented Fuel Assembly 430 (IFA-430). The measurement program has been directed toward quantifying the release of the short-lived radioactive noble gases and iodines.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6062827
• Report Number(s): EGG-M-09883; CONF-830563-3; ON: DE83015139
• Resource Relation: Conference: Enlarged halden program group meeting, Loen, Norway, 23 May 1983; Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
FUEL PELLETS
FISSION PRODUCT RELEASE
PWR TYPE REACTORS
FUEL ASSEMBLIES
FUEL RODS
REACTOR CORES
TEMPERATURE DEPENDENCE
URANIUM DIOXIDE
ACTINIDE COMPOUNDS
CHALCOGENIDES
FUEL ELEMENTS
OXIDES
OXYGEN COMPOUNDS
PELLETS
REACTOR COMPONENTS
REACTORS
URANIUM COMPOUNDS
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled