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