HTGR Knowledge Base
Conference Article: Core design for nuclear process heat reactor
L'Homme, A.; Gouret, J. (CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France))Abstract
In this paper, we introduce the design we propose for the prismatic block core of a process heat HTGR, having a 833 MW thermal power and a core outlet helium temperature of 858oC. We give the reasons for the choice of the basic options and the main results of the physics and the thermal preliminary analysis.
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key words: Gas Cooled Reactor, Nuclear Technology
- Reference:
- Specialists' meeting on process heat applications technology. Juelich, Germany, F.R. 27 - 29 Nov 1979
- International Atomic Energy Agency, Vienna (Austria). International Working Group on High-Temperature Reactors.
- IWGHTR--6, pp:16-31
- International Atomic Energy Agency, Vienna (Austria). International Working Group on High-Temperature Reactors.