LWR spent-fuel radiochemical measurements and comparison with ORIGEN2 predictions

Conference · Fri Jan 01 04:00:00 EST 1988 · Transactions of the American Nuclear Society; (USA)

OSTI ID:5532920

Blahnik, D E; Jenquin, U P; Guenther, R J

The Materials Characterization Center (MCC) at Pacific Northwest Laboratory is responsible for providing characterized spent fuel, designated approved testing material (ATMs) for subsequent use in the investigation of nuclear waste disposal forms by the US Department of Energy geologic repository project. The ATMs are selected to assure that test material is available that has a representative range of characteristics important to spent-fuel behavior in a geologic repository. Burnup and fission gas release were the primary criteria for selecting the ATMs. The five spent-fuel ATMs (ATM-101, -103, -104, -105, and -106) currently being characterized by the MCC have rod average burnups ranging from 20 to 43 MWd/kg M, fission gas releases ranging from 0.2 to 11.2%, and are from both boiling water reactors and pressurized water reactors. Radiochemical analyses of the fuel included measurements of {sup 148}Nd (for fuel burnup), the isotopes of uranium and plutonium, and nuclides of importance to repository performance. Cladding samples were analyzed for {sup 14}C. The measured values of selected nuclides were compared with values obtained from calculations with the ORIGEN2 code that was used to predict isotopic quantities for all of the ATMS. Ratios of the ORIGEN2 calculated values to the measured values for ATM-103 and ATM-106 fuel are given.

• OSTI ID: 5532920
• Report Number(s): CONF-881011--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 57
• Country of Publication: United States
• Language: English

Related Subjects

052002* -- Nuclear Fuels-- Waste Disposal & Storage
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACTINIDES
BURNUP
BWR TYPE REACTORS
CHEMICAL ANALYSIS
COMPUTER CODES
ELEMENTS
ENERGY SOURCES
FISSION PRODUCT RELEASE
FISSION PRODUCTS
FUELS
ISOTOPES
MANAGEMENT
MATERIALS
MATERIALS TESTING
METALS
NATIONAL ORGANIZATIONS
NUCLEAR FUELS
O CODES
PLUTONIUM
PWR TYPE REACTORS
QUANTITATIVE CHEMICAL ANALYSIS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOCHEMICAL ANALYSIS
REACTOR MATERIALS
REACTORS
SPENT FUELS
TESTING
TRANSURANIUM ELEMENTS
URANIUM
US DOE
US ORGANIZATIONS
WASTE DISPOSAL
WASTE MANAGEMENT
WATER COOLED REACTORS
WATER MODERATED REACTORS