Fuel assembly for BWR type reactor
- 1. Nippon Atomic Industry Group Co. Ltd., Tokyo (Japan)
Description
Various considerations are applied to fuel rods for improving the fuel burnup degree. If a gap between the fuel rods is changed, this varies the easiness for the flow of coolants depending on places, to reduce the thermal margin. Then, it is noted for the distribution of stresses generated due to the difference of water pressure caused by the difference of water streams between the inside and the outside of a channel box, and composite value, of stresses upon occurrence of earthquakes, neutron irradiation and a channel creep phenomenon caused by the stresses of due to the water pressure difference described above, the thickness of the channel box is increased in the upstream and decreased toward the downstream. Further, fuel spacers at the position where the thickness of the channel box is changed are spaced apart from the channel box so as not to brought into contact with the channel box. This can contribute to the reduction of coolants pressure loss, improvement of critical power and improvement of reactivity, as well as remarkably moderate local stresses applied from the fuel spacers to the channel box due to horizontal vibrations upon occurrence of earthquakes to improve the integrity of fuel assembly. (N.H.)
Availability note (English)
Available from JAPIO. Also available from INPADOC.Additional details
Publishing Information
- Imprint Pagination
- 6 p.
- IPC:
- Int. Cl. G21C3/324; G21C3/34.
- IPC
- Int. Cl. G21C3/324; G21C3/34.
- Patent number
- JP patent document 2-147888/A/
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 22016689
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; CLEARANCE; COOLANTS; CREEP; FLUID FLOW; FUEL ASSEMBLIES; FUEL RODS; PRESSURE GRADIENTS; REACTOR LATTICES; REACTOR SAFETY; SEISMIC EFFECTS; SPACERS; STRESSES; THICKNESS
- Descriptors DEC
- DIMENSIONS; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; MECHANICAL PROPERTIES; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- JP patent application 63-299564.