Investigation of the void coefficient and other integral parameters in the PROTEUS-LWHCR phase II program
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:7226978
Comparisons of calculated and measured neutron balance components are reported for the 7.5% fissile plutonium reference test lattice of the PROTEUS-light water high conversion reactor (LWHCR) phase II program, both wet (with H/sub 2/O) and dry (100% void). Special experimental techniques have been developed and applied, particularly for kappa/sub infinity/, and the range of directly measured reaction rate ratios has been extended. For the two cell codes tested, WIMS-D/1981 library and KARBUS/KEDAK-4, specific shortcomings have been identified; the new measurements have been found to be significantly more representative and accurate than the earlier phase I experiments. The kappa/sub infinity/ void coefficient for the phase II reference lattice between 0 and 100% void has been found to be qualitatively different from those assessed for the earlier phase I test lattices. Consideration of the individual void coefficient components show this to be largely a consequence of the more LWHCR-representative fuel rod diameter and plutonium isotopic composition of the fuel currently being used. Results of control rod studies conducted for the phase II reference lattice - both wet and dry - serve to illustrate the efforts being made toward investigations of special power reactor features.
- Research Organization:
- Swiss Federal Institute for Reactor Research, 5303 Wurenlingen (CH)
- OSTI ID:
- 7226978
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 80:2; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
ACTINIDES
COMPUTER CALCULATIONS
COMPUTER CODES
CONTROL ELEMENTS
ELEMENTS
ENRICHED URANIUM REACTORS
FUEL ELEMENTS
FUEL RODS
GRAPHITE MODERATED REACTORS
HYDROGEN COMPOUNDS
ISOTOPE RATIO
K CODES
METALS
NEUTRON FLUX
OXYGEN COMPOUNDS
PLUTONIUM
PROTEUS REACTOR
RADIATION FLUX
REACTOR COMPONENTS
REACTOR LATTICES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
TEST REACTORS
TESTING
TRANSURANIUM ELEMENTS
VOIDS
W CODES
WATER
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
ACTINIDES
COMPUTER CALCULATIONS
COMPUTER CODES
CONTROL ELEMENTS
ELEMENTS
ENRICHED URANIUM REACTORS
FUEL ELEMENTS
FUEL RODS
GRAPHITE MODERATED REACTORS
HYDROGEN COMPOUNDS
ISOTOPE RATIO
K CODES
METALS
NEUTRON FLUX
OXYGEN COMPOUNDS
PLUTONIUM
PROTEUS REACTOR
RADIATION FLUX
REACTOR COMPONENTS
REACTOR LATTICES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
TEST REACTORS
TESTING
TRANSURANIUM ELEMENTS
VOIDS
W CODES
WATER