Three-dimensional nodal diffusion and transport methods for the analysis of fast-reactor critical experiments
Conference
·
OSTI ID:6837556
This paper describes two new nodal methods for solving the multigroup neutron diffusion and transport equations in three-dimensional Cartesian geometry. These methods have been developed for the global analysis of fast-reactor critical experiments once cell-averaged multigroup cross sections for each matrix position or drawer have been computed using appropriate cell-homogenization procedures. Brief descriptions of the nodal diffusion and transport schemes are presented, along with results of two- and three-dimensional calculations for a current Zero Power Plutonium Reactor (ZPPR) configuration.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6837556
- Report Number(s):
- CONF-840901-6; ON: DE84011707
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
DIFFERENTIAL EQUATIONS
EPITHERMAL REACTORS
EQUATIONS
EXPERIMENTAL REACTORS
FAST REACTORS
MOCKUP
MULTIGROUP THEORY
NEUTRAL-PARTICLE TRANSPORT
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
PHYSICS
RADIATION TRANSPORT
REACTOR PHYSICS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
STRUCTURAL MODELS
TRANSPORT THEORY
ZERO POWER REACTORS
ZPPR REACTOR
210500* -- Power Reactors
Breeding
DIFFERENTIAL EQUATIONS
EPITHERMAL REACTORS
EQUATIONS
EXPERIMENTAL REACTORS
FAST REACTORS
MOCKUP
MULTIGROUP THEORY
NEUTRAL-PARTICLE TRANSPORT
NEUTRON DIFFUSION EQUATION
NEUTRON TRANSPORT
NEUTRON TRANSPORT THEORY
PHYSICS
RADIATION TRANSPORT
REACTOR PHYSICS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
STRUCTURAL MODELS
TRANSPORT THEORY
ZERO POWER REACTORS
ZPPR REACTOR