Three dimensional evaluation of two-phase flow in BWR fuel bundles based on compressible two fluid-one pressure and κ-ε turbulence models
- 1. Toden Software Inc., Tokyo (Japan). In-Core Fuel Management Systems Dept.
Description
The three dimensional fluid dynamic code system was developed to simulate a comprehensive two-phase flow field in fuel bundles of boiling water reactors. The system is based on the compressible two fluid-one pressure (six equations) model and is designed to be applicable to both detailed fully three dimensional geometries and porous medium sub-channel type geometries. In the detailed modeling, the turbulence effect is considered by the additional four conservation equations of the κ-ε turbulence model and the convective terms are formulated by the modified skewed upwind scheme. The sub-channel type modeling, in contrast, is built from coarser meshes. The empirical void drift and turbulence mixing models are introduced to replace the κ-ε turbulence model and other additional constitutive models such as the local loss are added to facilitate efficient sub-channel-type calculations. General problems were investigated regarding numerical methodologies in discretizing a vapor-liquid two-phase flow field based on the two fluid-one pressure model. The performances of several pressure iteration schemes were compared in combination with the outer Newton-Raphson iteration loop. (Author)
Additional details
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 25
- Journal Issue
- 7
- Journal Page Range
- p. 437-463.
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 29017995
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- BWR TYPE REACTORS; COMPRESSIBLE FLOW; FUEL ELEMENT CLUSTERS; REACTOR KINETICS; SIMULATION; THREE-DIMENSIONAL CALCULATIONS; TURBULENT FLOW; TWO-PHASE FLOW
- Descriptors DEC
- ENRICHED URANIUM REACTORS; FLUID FLOW; FUEL ASSEMBLIES; KINETICS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS