Published June 1975
| Version v1
Report
Irradiation performance of low density pellet
- 1. Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)
Description
The low-density uranium oxide pellets in zircaloy-2 cladding were irradiated in a reactor to investigate the in-pile sintering behavior. The pellets were prepared by cold-pressing uranium oxide fine powder and subsequent sintering at 800 degree C in reducing atmosphere. Those irradiated at low linear heat rating were broken into pieces, while those at high linear heat rating exhibited restructuring pattern, distinct central void and fuel-cladding clearance. The in-pile sintering of the pellets was apparent in both cases. (Mori, K.)
Additional details
Publishing Information
- Imprint Title
- Semi-annual progress report of Power Reactor and Nuclear Fuel Development Corporation, Tokai Works
- Imprint Pagination
- p. 65-71.
- Report number
- PNCT--831-75-01
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 8315759
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- COLD PRESSING; DENSITY; FUEL DENSIFICATION; FUEL PELLETS; FUEL PINS; IRRADIATION; NEUTRON BEAMS; RADIATION EFFECTS; SINTERING; SPECIFICATIONS; TIME DEPENDENCE; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; BEAMS; CHALCOGENIDES; FABRICATION; FUEL ELEMENTS; MATERIALS WORKING; NUCLEON BEAMS; OXIDES; OXYGEN COMPOUNDS; PARTICLE BEAMS; PHYSICAL PROPERTIES; PRESSING; REACTOR COMPONENTS; URANIUM COMPOUNDS; URANIUM OXIDES