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Characterization of LWR Spent Fuel Approved Testing Materials for Radionuclide Release Studies

Published online by Cambridge University Press:  26 February 2011

John O. Barner  and
J. L. Daniel
John O. Barner
Affiliation:
Pacific Northwest Laboratory Richland, WA 99352, USA
J. L. Daniel
Affiliation:
Pacific Northwest Laboratory Richland, WA 99352, USA
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Abstract

The Materials Characterization Center (MCC) provides characterized light-water reactor (LWR) spent fuel approved testing materials (ATMs) for use by experimenters in radionuclide release studies in support of repository licensing efforts. The characterization completed to date is described for MCC ATM-101, a Zircaloy-clad UO2 fuel from the H. B. Robinson, Unit 2, Assembly BO-5. ATM-101 is a moderate burnup, low-releasing (fission products in-reactor) spent fuel typical of the fuel that is expected to initially be placed in a repository.

Information

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 44: Symposium N – Scientific Basis for Nuclear Waste Management VIII , 1984 , 729
Copyright
Copyright © Materials Research Society 1985

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References

1. Barner, J. O. 1984. “LWR Spent Fuel Approved Testing Materials for Radionuclide Release Studies.” Pacific Northwest Laboratory, PNL-4686.Google Scholar
2. Barner, J. O. 1984. “Characterization of LWR Spent Fuel MCC-Approved Testing Materials-ATM-101.” Pacific Northwest Laboratory, PNL-5109.Google Scholar
3. Einziger, R. E. and Fish, R. L.. 1982. “Characterization of LWR Spent Fuel Rods Used in the NRC Low-Temperature Whole Rod and Crud Performance Test.” Hanford Engineering Development Laboratory, NUREG/CR-2871 (HEDL-TME 82–27).Google Scholar
4. Annual Book of ASTM Standards. 1980. Part 11. ASTM E112, Standard Methods for Estimating the Average Grain Size of Metals. pp. 186–220.Google Scholar
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