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Title: Characterization of spent fuel approved testing material: ATM-106

The characterization data obtained to date are described for Approved Testing Material (ATM)-106 spent fuel from Assembly BT03 of pressurized-water reactor Calvert Cliffs No. 1. This report is one in a series being prepared by the Materials Characterization Center at Pacific Northwest Laboratory on spent fuel ATMs. The ATMs are receiving extensive examinations to provide a source of well- characterized spent fuel for testing in the US Department of Energy Office of Civilian Radioactive Waste Management (OCWRM) program. ATM-106 consists of 20 full-length irradiated fuel rods with rod-average burnups of about 3700 GJ/kgM (43 MWd/kgM) and expected fission gas release of /approximately/10%. Characterization data include (1) as-fabricated fuel design, irradiation history, and subsequent storage and handling; (2) isotopic gamma scans; (3) fission gas analyses; (4) ceramography of the fuel and metallography of the cladding; (5) calculated nuclide inventories and radioactivities in the fuel and cladding; and (6) radiochemical analyses of the fuel and cladding. Additional analyses of the fuel rod are being conducted and will be included in planned revisions of this report. 12 refs., 110 figs., 81 tabs.
Authors:
; ; ; ; ;
Publication Date:
OSTI Identifier:
6755761
Report Number(s):
PNL-5109-106
ON: DE89002112; TRN: 88-035420
DOE Contract Number:
AC06-76RL01830
Resource Type:
Technical Report
Resource Relation:
Other Information: Portions of this document are illegible in microfiche products
Research Org:
Pacific Northwest Lab., Richland, WA (USA)
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY; CALVERT CLIFFS-1 REACTOR; SPENT FUELS; BURNUP; EVALUATION; FISSION PRODUCT RELEASE; FISSION PRODUCTS; FUEL CANS; FUEL ELEMENTS; IRRADIATION; NUCLEAR MATERIALS MANAGEMENT; O CODES; RADIOACTIVE WASTE MANAGEMENT; RADIOCHEMICAL ANALYSIS; TESTING; ZIRCALOY 4; ALLOYS; CHEMICAL ANALYSIS; COMPUTER CODES; ENERGY SOURCES; FUELS; ISOTOPES; MANAGEMENT; MATERIALS; NUCLEAR FUELS; POWER REACTORS; PWR TYPE REACTORS; QUANTITATIVE CHEMICAL ANALYSIS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; TIN ALLOYS; WASTE MANAGEMENT; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS 050800* -- Nuclear Fuels-- Spent Fuels Reprocessing; 210200 -- Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled; 400700 -- Radiochemistry & Nuclear Chemistry