Microstructural characteristics of PWR [pressurized water reactor] spent fuel relative to its leaching behavior

Conference · Wed Jan 01 00:00:00 EST 1986

OSTI ID:60346

Wilson, C N

Microstructural, compositional and thermochemical properties of spent nuclear fuel are discussed relative to its potential performance as a high-level waste form under proposed Nevada Nuclear Waste Storage Investigations Project tuff repository conditions. Pressurized water reactor spent fuel specimens with various artificially induced cladding defects were leach tested in deionized water and in a reference tuff groundwater under ambient hot cell air and temperature conditions. Greater fractional actinide release was observed with bare fuel than with clad fuel leached through a cladding defect. Congruent actinide release and preferential release of cesium and technetium were observed in both water types. Selected summary radionuclide release data are presented and correlated to pre- and post-test microstructural characterization data.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (United States)
• DOE Contract Number: AC06-76FF02170
• OSTI ID: 60346
• Report Number(s): HEDL-SA-3313-Rev.; CONF-850536-11-Rev.; ON: DE88001465
• Resource Relation: Conference: American Ceramic Society annual meeting, Cincinnati, OH (United States), 5-9 May 1985; Other Information: PBD: Jan 1986
• Country of Publication: United States
• Language: English

Related Subjects

21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
05 NUCLEAR FUELS
29 ENERGY PLANNING AND POLICY
PWR TYPE REACTORS
SPENT FUELS
MICROSTRUCTURE
LEACHING
RADIOACTIVE WASTE STORAGE
DISSOLUTION
CESIUM
TECHNETIUM
ACTINIDES
GROUND WATER
RADIOACTIVE WASTE FACILITIES
RADIOISOTOPES
FUEL CANS
URANIUM DIOXIDE
CHEMICAL PROPERTIES
GRAIN BOUNDARIES
Yucca Mountain Project