Nuclear fuel rods
Description
Purpose: To avoid reduction of fracture stresses in fuel cans by applying a beryllium-copper thin layer to the inner surface of the fuel cans. Constitution: A beryllium-copper thin layer is plated and sintered onto the oxide film on the inner circumferential surface of a cylindrical fuel can made of zirconium alloy and formed with the oxide film at its inner and outer circumferential surfaces by way of autoclaving. The fuel can thus formed with the beryllium-copper thin layer on its inner circumferential surface is welded, at its lower opening, with an end plug, charged with nuclear fuel pellets, replaced with helium, mounted with a pressor plate, a plenum spring or the like and finally welded with an upper end plug to constitute a fuel rod. (Kawakami, Y.)
Availability note (English)
Available from JAPATIC. Also available from INPADOC.Additional details
Publishing Information
- Imprint Pagination
- 3 p.
- IPC:
- Int. Cl. G21C3/20.
- IPC
- Int. Cl. G21C3/20.
- Patent number
- JP patent document 56-166492/A/
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 14746716
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- AUTOCLAVES; BERYLLIUM ADDITIONS; COPPER ALLOYS; CORROSION PROTECTION; FUEL CANS; PLATING; STRESS CORROSION; ZIRCONIUM ALLOYS; ZIRCONIUM OXIDES
- Descriptors DEC
- ALLOYS; CHALCOGENIDES; CHEMICAL REACTIONS; CORROSION; DEPOSITION; OXIDES; OXYGEN COMPOUNDS; SURFACE COATING; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENT COMPOUNDS; ZIRCONIUM COMPOUNDS