IMPROVEMENTS IN OR RELATING TO NUCLEAR FUEL MATERIALS
Patent
·
OSTI ID:4841201
A ceramic fuel material consisting of a fissile oxidedispersed in a nonfissile oxide is described which has very low permeability to fission product gases at high temperatures. The nonfissile oxide may be Al/sub 2/O/sub 3/, MgO, BeO, or ZrO/sub 2/ to which an additional oxide, such as SiO/sub 2/. is added to cause the formation of a liquid phase during sintering. The preferable oxide, however, is an aluminous porcelain containing Al/sub 2/O/sub 3/, SiO/sub 2/, MgO, and CaO mixed in the proportions 87: 10:2: 1 by weight and melting at 1500 deg C. Several examples of fuel material prepared using such mixtures are described. (D.L.C.)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-15-028790
- OSTI ID:
- 4841201
- Report Number(s):
- GB 874964
- Country of Publication:
- United Kingdom
- Language:
- English
Similar Records
Method for manufacturing targets for the production of plutonium, and targets thus obtained
THERMAL CONDUCTIVITY OF BERYLLIA CERAMICS FROM-200 TO 150 C
MARITIME GAS-COOLED REACTOR PROGRAM. TECHNICAL FEASIBILITY STUDIES OF FABRICATION TECHNIQUES APPLICABLE TO THE MANUFACTURE OF HIGH-DENSITY BERYLLIA TUBES FOR POTENTIAL UTILIZATION IN THE MARITIME GAS-COOLED REACTOR. Final Report, May 9 to June 30, 1960
Patent
·
Mon Feb 26 23:00:00 EST 1973
·
OSTI ID:4118370
THERMAL CONDUCTIVITY OF BERYLLIA CERAMICS FROM-200 TO 150 C
Journal Article
·
Thu Feb 28 23:00:00 EST 1963
· Journal of the American Ceramic Society (U.S.)
·
OSTI ID:4752530
MARITIME GAS-COOLED REACTOR PROGRAM. TECHNICAL FEASIBILITY STUDIES OF FABRICATION TECHNIQUES APPLICABLE TO THE MANUFACTURE OF HIGH-DENSITY BERYLLIA TUBES FOR POTENTIAL UTILIZATION IN THE MARITIME GAS-COOLED REACTOR. Final Report, May 9 to June 30, 1960
Technical Report
·
Tue Oct 30 23:00:00 EST 1962
·
OSTI ID:4833170