Published November 2002 | Version v1
Report

Thermohydraulics computer code system and computational results on thermal striping phenomena at a tee junction of LMFR circuit with the system

Creators

  • 1. O-arai Engineering Center (Japan)

Description

At the first half, thermal striping evaluation system consisted of the four thermohydraulics computer programs AQUA. DINUS-3, THEMIS and BEMSET, which are represented by a time-and volume-averaged transport analysis, a direct numerical simulation of turbulence flows, a direct simulation Monte Carlo analysis of the continuous fluid flows and a boundary element analysis of structures, respectively, were presented for the evaluation of thermal striping phenomena. This phenomena are recognized as one key unresolved issues from the standpoint of structural integrity of the in-vessel components of a liquid-metal fast reactor. Secondly, numerical results were indicated for the benchmark exercise on thermal striping phenomena at a tee junction pipe coordinated by International Atomic Energy Agency (IAEA). Then the calculated temperature on the outer metal surface of the main pipe was compared with the measured data. (author)

Part of:
Validation of fast reactor thermomechanical and thermohydraulic codes. Final report of a co-ordinated research project. 1996-1999

Additional details

Publishing Information

ISBN
92-0-118302-X
Imprint Title
Validation of fast reactor thermomechanical and thermohydraulic codes. Final report of a co-ordinated research project. 1996-1999
Imprint Pagination
262 p.
Journal Page Range
p. 117-144
ISSN
1011-4289
Report number
IAEA-TECDOC--1318

INIS

Optional Information

Notes
25 refs, 26 figs