Fast Reactors and Accelerator Driven Systems Knowledge Base

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

Muramatsu, T. (O-arai Engineering Center (Japan))

Abstract

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.

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key words: comparative evaluations; computer codes; fluid mechanics; lmfbr type reactors; monte carlo method; pipe joints; thermal analysis; thermal stresses; turbulent flow
Reference:
Final report of a co-ordinated research project 1996-1999
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--1318, pp:117-144