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Title: Radiochemical analyses of several spent fuel Approved Testing Materials

Abstract

Radiochemical characterization data are described for UO{sub 2} and UO{sub 2} plus 3 wt% Gd{sub 2}O{sub 3} commercial spent nuclear fuel taken from a series of Approved Testing Materials (ATMs). These full-length nuclear fuel rods include MLA091 of ATM-103, MKP070 of ATM-104, NBD095 and NBD131 of ATM-106, and ADN0206 of ATM-108. ATMs 103, 104, and 106 were all irradiated in the Calvert Cliffs Nuclear Power Plant (Reactor No.1), a pressurized-water reactor that used fuel fabricated by Combustion Engineering. ATM-108 was part of the same fuel bundle designed as ATM-105 and came from boiling-water reactor fuel fabricated by General Electric and irradiated in the Cooper Nuclear Power Plant. Rod average burnups and expected fission gas releases ranged from 2,400 to 3,700 GJ/kgM. (25 to 40 Mwd/kgM) and from less than 1% to greater than 10%, respectively, depending on the specific ATM. The radiochemical analyses included uranium and plutonium isotopes in the fuel, selected fission products in the fuel, fuel burnup, cesium and iodine on the inner surfaces of the cladding, {sup 14}C in the fuel and cladding, and analyses of the gases released to the rod plenum. Supporting examinations such as fuel rod design and material descriptions, power histories, and gammamore » scans used for sectioning diagrams are also included. These ATMs were examined as part of the Materials Characterization Center Program conducted at Pacific Northwest Laboratory provide a source of well-characterized spent fuel for testing in support of the US Department of Energy Office of Civilian Radioactive Waste Management Program.« less

Authors:
; ;
Publication Date:
Research Org.:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
10186049
Report Number(s):
PNL-10113
ON: DE95000772; TRN: 94:020379
DOE Contract Number:  
AC06-76RL01830
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Sep 1994
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEAR CHEMISTRY; SPENT FUELS; RADIOCHEMICAL ANALYSIS; URANIUM DIOXIDE; GADOLINIUM OXIDES; RADIOACTIVE WASTE MANAGEMENT; STANDARDS; CALVERT CLIFFS-1 REACTOR; COOPER REACTOR; FISSION PRODUCTS; IODINE 129; CARBON 14; CESIUM 135; CESIUM 137; HISTORICAL ASPECTS; IRRADIATION; URANIUM ISOTOPES; PLUTONIUM ISOTOPES; SELENIUM 79; STRONTIUM 90; TECHNETIUM 99; TIN 126; NEPTUNIUM 237; AMERICIUM 241; CURIUM 243; CURIUM 244; EXPERIMENTAL DATA; COMPILED DATA; 052000; 400702; WASTE MANAGEMENT; PROPERTIES OF RADIOACTIVE MATERIALS

Citation Formats

Guenther, R J, Blahnik, D E, and Wildung, N J. Radiochemical analyses of several spent fuel Approved Testing Materials. United States: N. p., 1994. Web. doi:10.2172/10186049.
Guenther, R J, Blahnik, D E, & Wildung, N J. Radiochemical analyses of several spent fuel Approved Testing Materials. United States. https://doi.org/10.2172/10186049
Guenther, R J, Blahnik, D E, and Wildung, N J. 1994. "Radiochemical analyses of several spent fuel Approved Testing Materials". United States. https://doi.org/10.2172/10186049. https://www.osti.gov/servlets/purl/10186049.
@article{osti_10186049,
title = {Radiochemical analyses of several spent fuel Approved Testing Materials},
author = {Guenther, R J and Blahnik, D E and Wildung, N J},
abstractNote = {Radiochemical characterization data are described for UO{sub 2} and UO{sub 2} plus 3 wt% Gd{sub 2}O{sub 3} commercial spent nuclear fuel taken from a series of Approved Testing Materials (ATMs). These full-length nuclear fuel rods include MLA091 of ATM-103, MKP070 of ATM-104, NBD095 and NBD131 of ATM-106, and ADN0206 of ATM-108. ATMs 103, 104, and 106 were all irradiated in the Calvert Cliffs Nuclear Power Plant (Reactor No.1), a pressurized-water reactor that used fuel fabricated by Combustion Engineering. ATM-108 was part of the same fuel bundle designed as ATM-105 and came from boiling-water reactor fuel fabricated by General Electric and irradiated in the Cooper Nuclear Power Plant. Rod average burnups and expected fission gas releases ranged from 2,400 to 3,700 GJ/kgM. (25 to 40 Mwd/kgM) and from less than 1% to greater than 10%, respectively, depending on the specific ATM. The radiochemical analyses included uranium and plutonium isotopes in the fuel, selected fission products in the fuel, fuel burnup, cesium and iodine on the inner surfaces of the cladding, {sup 14}C in the fuel and cladding, and analyses of the gases released to the rod plenum. Supporting examinations such as fuel rod design and material descriptions, power histories, and gamma scans used for sectioning diagrams are also included. These ATMs were examined as part of the Materials Characterization Center Program conducted at Pacific Northwest Laboratory provide a source of well-characterized spent fuel for testing in support of the US Department of Energy Office of Civilian Radioactive Waste Management Program.},
doi = {10.2172/10186049},
url = {https://www.osti.gov/biblio/10186049}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Sep 01 00:00:00 EDT 1994},
month = {Thu Sep 01 00:00:00 EDT 1994}
}