Characterization of spent fuel approved testing material--ATM-104
Author(s) -
R.J. Guenther,
D.E. Blahnik,
U.P. Jenquin,
J.E. Mendel,
L. E. Thomas,
C. K. Thornhill
Publication year - 1991
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/138327
Subject(s) - spent nuclear fuel , cladding (metalworking) , nuclide , fission products , spent fuel pool , burnup , nuclear engineering , materials science , fission , waste management , pressurized water reactor , nuclear fuel , radiochemistry , environmental science , radioactive waste , chemistry , metallurgy , nuclear physics , engineering , neutron , physics
The characterization data obtained to date are described for Approved Testing Material 104 (ATM-104), which is spent fuel from Assembly DO47 of the Calvert Cliffs Nuclear Power Plant (Unit 1), a pressurized-water reactor. This report is one in a series being prepared by the Materials Characterization Center at Pacific Northwest Laboratory (PNL) 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 (OCRWM) Program. ATM-104 consists of 128 full-length irradiated fuel rods with rod-average burnups of about 42 MWd/kgM and expected fission gas release of about 1%. A variety of analyses were performed to investigate cladding characteristics, radionuclide inventory, and redistribution of fission products. Characterization data include (1) fabricated fuel design, irradiation history, and subsequent storage and handling history; (2) isotopic gamma scans; (3) fission gas analyses; (4) ceramography of the fuel and metallography of the cladding; (5) special fuel studies involving analytical transmission electron microscopy (AEM) and electron probe microanalyses (EPMA); (6) calculated nuclide inventories and radioactivities in the fuel and cladding; and (7) radiochemical analyses of the fuel and cladding
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