On the preparation of graphite matrix fuels containing thorium carbide
Creators
- 1. Showa Denko K.K., Central Research Laboratory, Tokyo (Japan)
- 2. Showa Denko K.K., Head Office, Tokyo (Japan)
Description
With the aim of finding the most desirable set of conditions for powder metallurgical preparation of graphite matrix fuels containing thorium carbide, the properties and structure of fuel samples prepared by compacting various mixtures of powdered material followed by heating were investigated. It was found that of the resulting compacts those consisting of (1) purified and milled natural graphite powder, (2) metallic thorium powder and (3) furfuryl alcohol as binder showed the best properties after heating to 600℃. These compacts possessed 1.90∼2.40 g/cc density, 3.5∼10.0 kg/mm2 Vickers hardness, a thermal expansion coefficient at 900℃ of about 14 x 10-6/℃ in the direction parallel to, and 2.5 x 10-6/℃ normal to pressing direction, and a thermal conductivity, in the same temperature range, of 0.02 (parallel) and 0.07 cal/cm · sec℃ (normal). Since these favorable properties and structural features are not impaired by heating to about 2,000℃ subsequent to treatment at 600℃, it can be said that a new, simple and effective set of conditions for fuel preparation has been found. (author)
Availability note (English)
Available from DOI: https://doi.org/10.1080/18811248.1969.9732851Additional details
Identifiers
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo) (Online)
- Journal Volume
- 6
- Journal Issue
- 3
- Journal Page Range
- p. 120-127
- ISSN
- 1881-1248
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 54040517
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- BREEDER REACTORS; COATED FUEL PARTICLES; FISSION PRODUCTS; GRAPHITE; HTGR TYPE REACTORS; NUCLEAR FUELS; PEBBLE BED REACTORS; POWDER METALLURGY; POWDERS; RECOILS; THERMAL CONDUCTIVITY; THERMAL EXPANSION; THORIUM CARBIDES; URANIUM 233
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; CARBIDES; CARBON; CARBON COMPOUNDS; ELEMENTS; ENERGY SOURCES; EVEN-ODD NUCLEI; EXPANSION; FUEL PARTICLES; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HEAVY ION DECAY RADIOISOTOPES; HEAVY NUCLEI; HOMOGENEOUS REACTORS; ISOTOPES; MATERIALS; METALLURGY; MINERALS; NEON 24 DECAY RADIOISOTOPES; NONMETALS; NUCLEI; PHYSICAL PROPERTIES; RADIOACTIVE MATERIALS; RADIOISOTOPES; REACTOR MATERIALS; REACTORS; SOLID HOMOGENEOUS REACTORS; SPONTANEOUS FISSION RADIOISOTOPES; THERMODYNAMIC PROPERTIES; THORIUM COMPOUNDS; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 17 refs., 7 figs., 2 tabs., 4 photos