Published 1989
| Version v1
Book
Subchannel analysis by the FIDAS code based on the three-fluid model
- 1. Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center
- 2. Nuclear Data Corp. Tokyo (Japan)
Description
The Film Dryout Analysis Code in Subchannels, FIDAS, has been developed with the main objective of predicting dryout and post-dryout heat transfer in channels and in rod bundles. In FIDAS, two-phase flow consisting of continuous liquid film, continuous vapor and entrained droplets is modeled by a three-fluid, three-field representation of 12 field equations, i.e. three continuity, three energy and six momentum equations. In this validation study of the code, inter-subchannel mixing models were examined. FIDAS satisfactorily predicted flow quality and mass flux in subchannels under typical operating conditions of a boiling water reactor, as comparisons with the experimental data of GE 3x3 and ISPRA 4x4 tests. (orig.)
Additional details
Publishing Information
- Publisher
- Braun.
- Imprint Place
- Karlsruhe (Germany, F.R.)
- ISBN
- 3-7650-1115-0
- Imprint Title
- Fourth international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4). Proceedings. Vol. 1
- Imprint Pagination
- 745 p.
- Journal Page Range
- p. 560-567.
Conference
- Title
- 4. international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4).
- Dates
- 10-13 Oct 1989.
- Place
- Karlsruhe (Germany, F.R.).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 22029361
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTERIZED SIMULATION; DRYOUT; FILM BOILING; FUEL ELEMENT CLUSTERS; HYDRAULICS; MATHEMATICAL MODELS; TWO-PHASE FLOW
- Descriptors DEC
- BOILING; ENRICHED URANIUM REACTORS; FLUID FLOW; FUEL ASSEMBLIES; PHASE TRANSFORMATIONS; POWER REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS