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Reduced Enrichment for Research and Test Reactors
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Nuclear Engineering is a Division of Argonne National Laboratory (Argonne), a U.S. Department of Energy (DOE) laboratory managed by The University of Chicago

Home  :: 1996 International RERTR Meeting Program  :: Related Documents

Abstracts and Available Papers Presented at the
1996 International RERTR Meeting

A CONCEPT OF LEU POOL TYPE HIGH FLUX RESEARCH REACTOR
WITH SOLID COOLANT

V. Artamkin, J. Chikhladze

Research and Development Institute of Power Engineering
Moscow 101 000, P.O. Box 788, RDIPE-NIKIET, Russia

ABSTRACT

A new concept of High Flux Reactor with Solid Coolant (HFRSC) is presented. Due to application of high temperature moving fuel with significant heat capacity, used to accumulate energy generated in the reactor core, it is possible to overcome technological and physical barriers limiting the values of neutron fluxes in case of traditional reactor design. For HFRSC MEU or LEU is a natural choice to ensure essential temperature coefficient of reactivity. Application of water in the reactor core only as a moderator creates an opportunity to avoid pressurized circuit and place reactor into pool with all the advantages both for reactor safety and easy access to experimental facilities. A comparison with traditional high flux research reactor concept (ANS) is presented.


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An electronic copy of the full paper is not available at this time. If you would like to receive a copy of this paper, please contact the author.


Contact:
Dr. Vadim N. Artamkin
Research and Development Institute of Power Engineering
PO Box 788
Moscow 101000, Russia
Tel.: +7-502-220-4991
Fax: +7-502-220-4978
E-mail: 6193357@MCIMAIL.COM

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Last modified on July 29, 2008 11:33 +0200