Argonne National Laboratory
RERTR
Reduced Enrichment for Research and Test Reactors
Nuclear Engineering Division at Argonne
U.S. Department of Energy

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Abstracts and Available Papers Presented at the
1998 International RERTR Meeting

VALIDATION AND VERIFICATION OF THE MTR_PC
THERMOHYDRAULIC PACKAGE

Alicia Doval
Nuclear Engineering Department, INVAP S.E.
F.P. Moreno 1089, P.O. Box 961
(8400) Bariloche, Rio Negro, Argentina

e-mail: doval@invap.com.ar

ABSTRACT

The MTR_PC v2.6 is a computational package developed for research reactor design and calculation. It covers three of the main aspects of a research reactor: neutronic, shielding and thermohydraulic. In this work only the thermohydraulic package will be covered, dealing with verification and validation aspects. The package consists of the following steady state programs: CAUDVAP 2.60 for the hydraulic calculus, estimates the velocity distribution through different parallel channels connected to a common inlet and outlet common plenum. TERMIC 1H v3.0, used for the thermal design of research reactors, provides information about heat flux for a given maximum wall temperature, onset of nucleate boiling, redistribution phenomena and departure from nucleate boiling. CONVEC V3.0 allows natural convection calculations, giving information on heat fluxes for onset of nucleate boiling, pulsed boiling and burn-out phenomena as well as total coolant flow. Results have been validated against experimental values and verified against theoretical and computational programmes results, showing a good agreement.


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Contact:
Alicia Doval
Nuclear Engineering Department - INVAP S.E.
F.P.Moreno 1089, CC 961
Bariloche Rio Negro 8400
Argentina

Phone: 54 944 22121
Fax: 54 944 21100
Email: doval@invap.com.ar

2016 RERTR Meeting

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2015 RERTR Meeting

The 2015 International RERTR Meeting (RERTR-2015) took place in Seoul, Korea on Oct. 11-14, 2015.
For more information visit RERTR-2015.

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Last modified on July 29, 2008 11:33 +0200