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.).