Published April 1977
| Version v1
Journal article
The future of the high temperature reactor
Creators
Description
The characteristics of the high temperature reactor which, in combination, lead to a high degree of safety and also to considerable development potential are described. The very satisfactory experiences gained from Dragon, Peach Bottom and the AVR pebble bed reactor, particularly in relation to helium technology, graphite core structure and fission product retention in coated fuel particles are discussed in some detail. Future prospects considered are the use of commercial steam cycle HTRs, the gas turbine HTR and the possible use of process heat. The medium and long-term role of HTRs is finally examined. (U.K.)
Additional details
Publishing Information
- Journal Title
- J. Br. Nucl. Energy Soc.
- Journal Volume
- 16
- Journal Issue
- 2
- Series
- J. Br. Nucl. Energy Soc.
- Journal Page Range
- 123-130
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 8322334
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AVR REACTOR; COATED FUEL PARTICLES; DRAGON REACTOR; FISSION PRODUCTS; GRAPHITE; HELIUM; HTGR TYPE REACTORS; PEACH BOTTOM-1 REACTOR; PERFORMANCE; REACTOR SAFETY
- Descriptors DEC
- CARBON; ELEMENTS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUEL PARTICLES; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HOMOGENEOUS REACTORS; ISOTOPES; NONMETALS; PEBBLE BED REACTORS; POWER REACTORS; RADIOACTIVE MATERIALS; RARE GASES; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SOLID HOMOGENEOUS REACTORS; THERMAL REACTORS; THORIUM REACTORS
Optional Information
- Notes
- Lecture sponsored by the British Nuclear Energy Society and given at the Institution of Civil Engineers, 18 November 1976.