Published October 13, 1988 | Version v1
Patent

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.