High temperature gas-cooled reactor
Technical Report
·
OSTI ID:4934938
From strategy for the development of nuclear steelmaking symposium; London, UK (6 Jun 1973). The advantages of HTR systems are presented. Core design is discussed and comparison is made between fuel elements for Fort St Vrain and for Dragon. Uses of HTR type reactors for multipurpose heat, high efficiency steam cycles and use with gas turbines are considered. Problems associated with the achievement of high temperatures, such as behavior of materials, particularly those for heat exchangers, and also problems of coolant impurity, are discussed. Some results of the Dragon experimental program on the behavior of stressed and unstressed specimens in HTR helium are summarized. (UK)
- Research Organization:
- UKAEA Reactor Group, Winfrith. Atomic Energy Establishment
- Sponsoring Organization:
- Sponsor not identified
- NSA Number:
- NSA-29-009326
- OSTI ID:
- 4934938
- Report Number(s):
- CONF-730668--2
- Country of Publication:
- United Kingdom
- Language:
- English
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