On the effect of different placing ZrH moderator material on the performance of a SFR core
- Helmholtz-Zentrum Dresden-Rossendorf, Institut fuer Sicherheitsforschung, Postfach 51 01 19, 01314 Dresden (Germany)
- Gesellschaft fuer Anlagen- und Reaktorsicherheit GRS MbH Forschungszentrum, Boltzmannstr. 14, 85748 Garching (Germany)
This study describes the development of a sodium fast reactor fuel assembly design with reduced void reactivity coefficient, achieved through the use of the ZrH moderating material. In the study the sodium void effect, as well as the major feedback coefficients are analyzed. Besides the feedback coefficients, the influence on the operational parameters like neutron flux distribution, power distribution, and burnup distribution is investigated for the different possibilities of arranging the moderating material in the fuel assembly. Additionally, the fuel cycle parameters - breeding and minor actinide production - are analyzed. For a first evaluation of the behavior during transients the influence of temperature changes in the ZrH is studied. (authors)
- Research Organization:
- American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)
- OSTI ID:
- 22105817
- Resource Relation:
- Conference: PHYSOR 2012: Conference on Advances in Reactor Physics - Linking Research, Industry, and Education, Knoxville, TN (United States), 15-20 Apr 2012; Other Information: Country of input: France; 15 refs.
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
BREEDING
BURNUP
DISTRIBUTION
FAST REACTORS
FEEDBACK
FUEL ASSEMBLIES
FUEL CYCLE
MODERATORS
NEUTRON FLUX
NUCLEAR FUELS
POWER DISTRIBUTION
REACTIVITY COEFFICIENTS
REACTOR FUELING
SODIUM
SODIUM COOLED REACTORS
VOIDS
ZIRCONIUM ALLOYS
ZIRCONIUM HYDRIDES