Skip to main content
OSTI.GOVU.S. Department of Energy Office of Scientific and Technical Information
U.S. Department of Energy
Office of Scientific and Technical Information
 

Current status of fuel degradation studies in dry storage

Conference ·
OSTI ID:6839721
;
Cladding integrity is an important consideration for the dry storage licensing position for LWR fuel that is developing in the USA. There is a large body of data and experience for zircaloy-clad fuel behavior during reactor service. Also, some 15,000 zircaloy-clad rods have been emplaced in dry storage demonstrations in metal casks, drywells, silos and vaults. This paper summarizes zircaloy cladding behavior as it applies to expected dry storage scenarios. 25 references, 5 figures, 3 tables.
Research Organization:
Pacific Northwest Lab., Richland, WA (USA)
DOE Contract Number:
AC06-76RL01830
OSTI ID:
6839721
Report Number(s):
PNL-SA-11894; CONF-840141-4; ON: DE84011250
Country of Publication:
United States
Language:
English

Similar Records

Spent fuel behavior in dry storage
Conference · Sun Jan 31 23:00:00 EST 1982 · OSTI ID:5366698
Behavior of spent nuclear fuel and storage system components in dry interim storage. Revision 1
Technical Report · Mon Jan 31 23:00:00 EST 1983 · OSTI ID:5534678
Dry storage of LWR spent fuel in the US: a status report
Conference · Fri Jun 01 00:00:00 EDT 1984 · OSTI ID:6380872

Related Subjects

050900* -- Nuclear Fuels-- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
CHEMICAL REACTIONS
CORROSION
COVER GAS
DEFECTS
DRY STORAGE
FLUIDS
FUEL CANS
GASES
INERT ATMOSPHERE
OXIDATION
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
SPENT FUEL STORAGE
STORAGE
TIN ALLOYS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS