Greek research reactor performance characteristics after addition of beryllium reflector and LEU fuel
Conference
·
OSTI ID:10107391
- Argonne National Lab., IL (United States)
- National Center for Scientific Research, Athens (Greece)
The GRR-1 is a 5-MW pool-type, light-water-moderated and-cooled reactor fueled with MTR-type fuel elements. Recently received Be reflector blocks will soon be added to the core to add additional reactivity until fresh LEU fuel arrives. REBUS-3 xy fuel cycle analyses, using burnup dependent cross sections, were performed to assist in fuel management decisions for the water- and Be-reflected HEU nonequilibrium cores. Cross sections generated by EPRI-CELL have been benchmarked to identical VIM Monte Carlo models. The size of the Be-reflected LEU core has been reduced to 30 elements compared to 35 for the HEU water-reflected core, and an equilibrium cycle calculation has been performed.
- Research Organization:
- Argonne National Lab., IL (United States); National Research Centre for the Physical Sciences Democritos, Athens (Greece)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 10107391
- Report Number(s):
- ANL/EP/CP-77803; CONF-9209266-2; ON: DE93002930
- Resource Relation:
- Conference: 1992 international meeting on reduced enrichment for research and test reactors,Roskilde (Denmark),27 Sep - 1 Oct 1992; Other Information: PBD: [1992]
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
DEMOCRITUS REACTOR
NUCLEAR FUELS
CONVERSION
SLIGHTLY ENRICHED URANIUM
HIGHLY ENRICHED URANIUM
NEUTRON REFLECTORS
CROSS SECTIONS
R CODES
E CODES
V CODES
BURNUP
REACTOR PHYSICS
FUEL ELEMENTS
PROLIFERATION
220600
350200
220100
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
THEORY AND CALCULATION
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
DEMOCRITUS REACTOR
NUCLEAR FUELS
CONVERSION
SLIGHTLY ENRICHED URANIUM
HIGHLY ENRICHED URANIUM
NEUTRON REFLECTORS
CROSS SECTIONS
R CODES
E CODES
V CODES
BURNUP
REACTOR PHYSICS
FUEL ELEMENTS
PROLIFERATION
220600
350200
220100
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
THEORY AND CALCULATION