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Conference Article: Thermal Hydraulic Simulations on High Temperature Reactors

Abstract

This paper describes two typical studies on thermal hydraulic problems on high temperature reactors. The first concerns the core heat transfer performance of a pebble bed core, the second deals with thermal stresses on the core outlet region of a high temperature reactor. These simulations are performed with the TRIO_U/PRICELES code developed by the C.E.A.

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Reference:

Proceedings of the Conference on High Temperature Reactors, Petten, NL, April 22-24, 2002
Organized by HTR-TN in cooperation with the European Nucler Society (ENS) and the IAEA

International Atomic Energy Agency, Vienna (Austria)

HTR-2002, pp:1-5