Determination of effective reflector and baffle/reflector constants for few-group diffusion calculations
Journal Article
·
· Nucl. Sci. Eng.; (United States)
OSTI ID:5053207
Analysis of critical experiments for cross-section evaluation has been conducted on the basis of one-dimensional four-group diffusion theory calculations that explicitly model the homogenized core and reflector in the radial plane. Such analyses require a reflector representation that models the leakage process as accurately as feasible. The development and testing of few-group ENDF/B-V based light water reflector constants for use in diffusion theory derived to reproduce leakage and other reaction rates from reference multifast group transport calculations are described. This work has been extended to parameterize similar higher order transport calculations with two- or four-group constants valid for application to typical pressurized water reactor baffle/reflector configurations as represented in coarse mesh diffusion (PDQ) representations.
- Research Organization:
- Electric Power Research Institute, Palo Alto, California
- OSTI ID:
- 5053207
- Journal Information:
- Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 90:2; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
Similar Records
Few-group baffle and/or reflector constants for diffusion calculation application
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Technical Report
·
Wed Aug 01 00:00:00 EDT 1984
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OSTI ID:6594496
Method of baffle/reflector region homogenization
Conference
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Tue Dec 31 23:00:00 EST 1985
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6907808
Linear discontinuous finite difference formulation for synthetic coarse-mesh few-group diffusion calculations
Journal Article
·
Sun Nov 30 23:00:00 EST 1986
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·
OSTI ID:6744647
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
COMPUTERIZED SIMULATION
DIFFERENTIAL EQUATIONS
DIFFUSION
EQUATIONS
KINETICS
MATHEMATICAL MODELS
MULTIGROUP THEORY
NEUTRON DIFFUSION EQUATION
NEUTRON LEAKAGE
NEUTRON REFLECTORS
NEUTRON TRANSPORT THEORY
NUCLEAR DATA COLLECTIONS
PHYSICAL PROPERTIES
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR KINETICS
REACTORS
REFLECTOR SAVINGS
SIMULATION
THERMAL DIFFUSION
THERMAL DIFFUSIVITY
THERMODYNAMIC PROPERTIES
TRANSPORT THEORY
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
COMPUTERIZED SIMULATION
DIFFERENTIAL EQUATIONS
DIFFUSION
EQUATIONS
KINETICS
MATHEMATICAL MODELS
MULTIGROUP THEORY
NEUTRON DIFFUSION EQUATION
NEUTRON LEAKAGE
NEUTRON REFLECTORS
NEUTRON TRANSPORT THEORY
NUCLEAR DATA COLLECTIONS
PHYSICAL PROPERTIES
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR KINETICS
REACTORS
REFLECTOR SAVINGS
SIMULATION
THERMAL DIFFUSION
THERMAL DIFFUSIVITY
THERMODYNAMIC PROPERTIES
TRANSPORT THEORY
WATER COOLED REACTORS
WATER MODERATED REACTORS