Method of manufacturing sintered oxide nuclear fuel
Description
Purpose: To reduce the increase in PCI due to increase in swelling, as well as reduce the releasing rate of FP gases. Method: UO2 powder and 15 wt% GD2O3- powder at the maximum are mixed, at the material ratio of Gd2O3-incorporated UO2 pellet, within a range of greater than 2.10 for O/M (M = U + Gd) and within a range from 2.10 to 2.20 for O/U ratio of UO2 powder, molded and then sintered. In this case, sintering is at first proceeded in a CO2 gas atmosphere mixed with air to such a degree as the crystal grain size is from 2 to 3 mm. Then, at the second step, the atmosphere is switched to H2 and the temperature is increased abruptly up to a temperature higher than 1700degC at such an rising rate as not causing cracking. This enables to obtain a sintering product in which the average crystal grain size at the outer circumferential portion is smaller than that in the inner side, thereby obtain the intended purpose. (Takahashi, M.)
Availability note (English)
Available from JAPIO. Also available from INPADOC.Additional details
Publishing Information
- Imprint Pagination
- 3 p.
- IPC:
- Int. Cl. G21C3/62.
- IPC
- Int. Cl. G21C3/62.
- Patent number
- JP patent document 63-246698/A/
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 20049375
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- FISSION PRODUCTS; GADOLINIUM OXIDES; GASES; MIXING; NUCLEAR FUELS; POWDERS; SINTERING; SWELLING; URANIUM OXIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; DEFORMATION; ENERGY SOURCES; FABRICATION; FLUIDS; FUELS; GADOLINIUM COMPOUNDS; ISOTOPES; MATERIALS; OXIDES; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; RARE EARTH COMPOUNDS; REACTOR MATERIALS; URANIUM COMPOUNDS
Optional Information
- Secondary number(s)
- JP patent application 62-77557.