Published March 1983
| Version v1
Report
Cladding deformation and fuel stack mechanical stability during internal pressurisation tests on irradiated PWR fuel
- 1. UKAEA Windscale Nuclear Power Development Labs.
Description
A description is given of the first phase of a programme of simulated LOCA tests on 450 mm lengths cut from PWR fuel rods that had been irradiated to 20 GWd/tU (rod average). The primary purpose of the work is to examine the mechanical stability of the fuel column when the cladding has bulged away from it under internal pressurisation and to evaluate the extent of fuel fragmentation and re-location that occurs. (U.K.)
Availability note (English)
Available from HMSO, London, price Pound2.00.Additional details
Publishing Information
- Imprint Pagination
- 29 p.
- Report number
- ND-R--628(W)
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 14783970
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- DEFORMATION; FUEL CANS; FUEL PELLETS; FUEL RODS; LOSS OF COOLANT; MECHANICAL FRAGMENTATION; PWR TYPE REACTORS; SPENT FUEL ELEMENTS; TESTING; URANIUM DIOXIDE; ZIRCALOY
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; ALLOYS; CHALCOGENIDES; FUEL ELEMENTS; OXIDES; OXYGEN COMPOUNDS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS