Properties of spent fuel
Description
The properties of spent fuel from current commercial nuclear power plants are discussed. These fuel rod designs utilize Zircaloy tubular cladding filled with uranium dioxide (UO2) pellets. During reactor operation, various chemical and physical changes take place in the fuel and cladding due to neutronic and thermal processes. The processes and changes are reviewed. The major topics are as follows: fission product formation, fission product relocation and release, pellet cracking and relocation, fuel-to-cladding interaction, and Zircaloy growth and embrittlement. The chemical and physical properties of reactor fuel after achieving its designed irradiation exposure are described. The integrity of spent fuel rods is discussed as it relates to short and long term storage. 11 figures, 1 table
Additional details
Publishing Information
- Imprint Title
- High-level radioactive solid waste forms
- Journal Page Range
- p. 561-595.
- Report number
- NUREG/CP--0005
Conference
- Title
- Conference on high-level radioactive solid waste.
- Dates
- 19 - 21 Dec 1978.
- Place
- Denver, CO, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11504657
- Subject category
- S38: RADIATION CHEMISTRY, RADIOCHEMISTRY AND NUCLEAR CHEMISTRY; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CHEMICAL PROPERTIES; CLADDING; FISSION PRODUCT RELEASE; FUEL PELLETS; NUCLEAR POWER PLANTS; PHYSICAL PROPERTIES; SPENT FUEL STORAGE; SPENT FUELS; URANIUM DIOXIDE; ZIRCALOY
- Descriptors DEC
- ACTINIDE COMPOUNDS; ALLOYS; CHALCOGENIDES; DEPOSITION; ENERGY SOURCES; FUELS; NUCLEAR FACILITIES; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; POWER PLANTS; REACTOR MATERIALS; STORAGE; SURFACE COATING; THERMAL POWER PLANTS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; URANIUM COMPOUNDS; URANIUM OXIDES; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS