Greek research reactor performance characteristics after addition of beryllium reflector and LEU fuel
Conference
·
OSTI ID:6959835
- 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:
- DOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6959835
- Report Number(s):
- ANL/EP/CP-77803; CONF-9209266--2; ON: DE93002930
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
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98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
ACTINIDES
BURNUP
COMPUTER CODES
CONVERSION
CROSS SECTIONS
DEMOCRITUS REACTOR
E CODES
ELEMENTS
ENERGY SOURCES
ENRICHED URANIUM
ENRICHED URANIUM REACTORS
FUEL ELEMENTS
FUELS
HIGHLY ENRICHED URANIUM
ISOTOPE ENRICHED MATERIALS
MATERIALS
METALS
NEUTRON REFLECTORS
NUCLEAR FUELS
PHYSICS
POOL TYPE REACTORS
PROLIFERATION
R CODES
REACTOR COMPONENTS
REACTOR MATERIALS
REACTOR PHYSICS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SLIGHTLY ENRICHED URANIUM
THERMAL REACTORS
URANIUM
V CODES
WATER COOLED REACTORS
WATER MODERATED REACTORS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
350200 -- Arms Control-- Proliferation-- (1987-)
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
ACTINIDES
BURNUP
COMPUTER CODES
CONVERSION
CROSS SECTIONS
DEMOCRITUS REACTOR
E CODES
ELEMENTS
ENERGY SOURCES
ENRICHED URANIUM
ENRICHED URANIUM REACTORS
FUEL ELEMENTS
FUELS
HIGHLY ENRICHED URANIUM
ISOTOPE ENRICHED MATERIALS
MATERIALS
METALS
NEUTRON REFLECTORS
NUCLEAR FUELS
PHYSICS
POOL TYPE REACTORS
PROLIFERATION
R CODES
REACTOR COMPONENTS
REACTOR MATERIALS
REACTOR PHYSICS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SLIGHTLY ENRICHED URANIUM
THERMAL REACTORS
URANIUM
V CODES
WATER COOLED REACTORS
WATER MODERATED REACTORS