Fuel assembly
Description
The axial length of a natural uranium pellet charged in natural uranium regions at upper and lower axial ends of a fuel assembly, where the linear power density is relatively low, is made longer than the axial length of a uranium pellet charged in other axial regions of the fuel assembly. The upper limit for the axial length of the natural uranium pellet is defined as I/d = 30 (in which I represents the axial length and d represents the diameter of the natural uranium pellet). In view of the above, the number of the natural uranium pellets required for one fuel assembly can be reduced than usual and they can be discriminated at once visually due to the difference of the length. Accordingly, it is possible to facilitate the production management, suppress the occurrence of inferior concentration distribution, prevent the loss of the production efficiency and reduce the production cost. (T.M.)
Availability note (English)
Available from JAPIO. Also available from INPADOC.Additional details
Publishing Information
- Imprint Pagination
- 5 p.
- IPC:
- Int. Cl. G21C3/328; G21C3/28.
- IPC
- Int. Cl. G21C3/328; G21C3/28.
- Patent number
- JP patent document 2-44287/A/
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 21083745
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; DIMENSIONS; FABRICATION; FUEL ASSEMBLIES; FUEL PELLETS; FUEL RODS; HOMOGENIZATION METHODS; IDENTIFICATION SYSTEMS; NATURAL URANIUM; POWER DISTRIBUTION
- Descriptors DEC
- ACTINIDES; DISTRIBUTION; ELEMENTS; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; METALS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SPATIAL DISTRIBUTION; THERMAL REACTORS; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- JP patent application 63-193471.