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Title: Spent fuel dissolution studies FY 1991 to 1994

Technical Report ·
DOI:https://doi.org/10.2172/205055· OSTI ID:205055

Dissolution and transport as a result of groundwater flow are generally accepted as the primary mechanisms by which radionuclides from spent fuel placed in a geologic repository could be released to the biosphere. To help provide a source term for performance assessment calculations, dissolution studies on spent fuel and unirradiated uranium oxides have been conducted over the past few years at Pacific Northwest National Laboratory (PNNL) in support of the Yucca Mountain Site Characterization Project. This report describes work for fiscal years 1991 through 1994. The objectives of these studies and the associated conclusions, which were based on the limited number of tests conducted so far, are described in the following subsections.

Research Organization:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Organization:
USDOE, Washington, DC (United States)
DOE Contract Number:
AC06-76RL01830
OSTI ID:
205055
Report Number(s):
PNL-10540; ON: DE96007354; TRN: 96:008722
Resource Relation:
Other Information: PBD: Dec 1995
Country of Publication:
United States
Language:
English