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Conference Article: LEU-HTR critical experiment program for the PROTEUS facility in Switzerland

Brogli, R.; Bucher, K.H.; Chawla, R.; Foskolos, K.; Luchsinger, H.; Mathews, D.; Sarlos, G.; Seiler, R. (Paul Scherrer Institute, Laboratory for Reactor Physics and System Technology Wuerenlingen and Villigen, Villigen PSI (Switzerland))

Abstract

New critical experiments in the framework of an IAEA Coordinated Research Program on “Validation of Safety Related Reactor Physics Calculations for Low Enriched HTR’s” are planned at the PSI PROTEUS faciIity. The experiments are designed to supplement the experimental data base and reduce the design and licensing uncertainties for small- and medium-sized helium-cooled reactors using low-enriched uranium (LEU) and graphite high temperature fuel. The main objectives of the new experiments are to provide first-of-a-kind high quality experimental data on: 1) The criticality of simple, easy to interpret, single core region LEU HTR systems for several moderator-to-fuel ratios and several lattice geometries; 2) the changes in reactivity, neutron balance components and control rod effectiveness caused by water ingress into this type of reactor; and 3) the effects of the boron and/or hafnium absorbers that are used to modify the reactivity and the power distributions in typical HTR systems. Work on the de-sign and licensing of the modified PROTEUS critical facility is now in progress with the HTR experiments scheduled to begin early in 1991 Several international partners will be involved in the planning, execution and analysis of these experiments in order to insure that they are relevant and cost effective with respect to the various gas cooled reactor national programs.

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key words: burnable poisons; calculation methods; control rod worths; coordinated research programs; experiment planning; htgr type reactors; licensing procedures; moderator-fuel ratio; multiplication factors; neutron absorbers; performance testing; reactor cores; reactor licensing; slightly enriched uranium; validation
Reference:
Technical committee meeting on gas-cooled reactor technology safety and siting Dimitrovgrad (Russian Federation) 21-23 Jun 1989
International Atomic Energy Agency, Vienna (Austria)
IAEA-TC--389.26, pp:634-651