Published 1988 | Version v1
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Three-dimensional thermal-hydraulic analysis of a liquid metal reactor design with the COMMIX code

Description

Steady-state and transient thermal-hydraulic analysis of a liquid metal reactor (LMR) design have been performed with the COMMIX computer code and the results are discussed. The LMR design analyzed includes an inherent safety feature which enables the decay heat removal by natural convection of ambient air, and the purpose of this analysis is to evaluate the inherent safety feature of the LMR design. COMMIX is a three-dimensional thermal-hydraulic analysis computer code developed at Argonne National Laboratory. A single-phase version of COMMIX has been used. Radiation plays an important role in the overall heat transfer, and the COMMIX version used includes the radiation capability. The theoretical formulation of COMMIX, including the treatment of thermal structures and radiation, is also discussed. 6 refs., 8 figs

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A03/MF A01; 1 as DE88010067.

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Additional details

Publishing Information

Imprint Pagination
25 p.
Report number
CONF-881115--2

Conference

Title
3. international topical meeting on nuclear power plant thermal hydraulics and operations.
Dates
14-17 Nov 1988.
Place
Seoul (Republic of Korea).

Optional Information

Notes
Portions of this document are illegible in microfiche products.