Multiregion neutronics model based on coarse mesh nodal coupling method for transient analyses of boiling water reactors
Journal Article
·
· Nucl. Sci. Eng.; (United States)
OSTI ID:6978396
A coarse mesh nodal coupling method, a well-known technique often used in steady-state neutronics analysis of light water reactors, is extended to a problem of transient phenomena of boiling water reactors (BWRs). Spatial collapse is attempted to develop a multiregion neutronics model and the associated axially one-dimensional and one-point models. These models are numerically solved through the use of two approximations, quasi-static and prompt jump. The results as applied to a reference BWR core for transient analyses, initiated by artificial thermal-hydraulic disturbances, are presented to show the practicality of the approach. The nature of the optimal weighting function necessary for the spatial collapse and for the quasi-static approximation is also discussed. Refs.
- Research Organization:
- Hitachi Ltd, Ibaraki, Japan
- OSTI ID:
- 6978396
- Journal Information:
- Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 80:4; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
BWR TYPE REACTORS
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
KINETICS
MATHEMATICAL MODELS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
RADIATION TRANSPORT
REACTOR KINETICS
REACTORS
THERMAL POWER PLANTS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
BWR TYPE REACTORS
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
KINETICS
MATHEMATICAL MODELS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
RADIATION TRANSPORT
REACTOR KINETICS
REACTORS
THERMAL POWER PLANTS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS