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Title: Test plan for thermogravimetric analyses of BWR spent fuel oxidation

Preliminary studies indicated the need for additional low-temperature spent fuel oxidation data to determine the behavior of spent fuel as a waste form for a tuffy repository. Short-term thermogravimetric analysis tests were recommended in a comprehensive technical approach as the method for providing scoping data that could be used to (1) evaluate the effects of variables such as moisture and burnup on the oxidation rate, (2) determine operative mechanisms, and (3) guide long-term, low-temperature oxidation testing. The initial test series studied the temperature and moisture effects on pressurized water reactor fuel as a function of particle and grain size. This document presents the test matrix for studying the oxidation behavior of boiling water reactor fuel in the temperature range of 140 to 225{degree}C. 17 refs., 7 figs., 3 tabs.
Authors:
Publication Date:
OSTI Identifier:
60652
Report Number(s):
PNL-6745
ON: DE89006389; TRN: 89:003752
DOE Contract Number:
AC06-76RL01830
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Dec 1988
Research Org:
Pacific Northwest Lab., Richland, WA (United States)
Country of Publication:
United States
Language:
English
Subject:
05 NUCLEAR FUELS; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; OXIDATION; THERMAL GRAVIMETRIC ANALYSIS; SPENT FUELS; SPENT FUEL STORAGE; TUFF; BWR TYPE REACTORS; TESTING; DATA ANALYSIS; MOISTURE; PARTICLE SIZE; QUALITY ASSURANCE; EXPERIMENTAL DATA; X-RAY DIFFRACTION; ELECTRON MICROSCOPY; CERAMOGRAPHY; Yucca Mountain Project