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Analyses of the TRACE V5 Capability for the Simulation of Natural Circulation and Primary/Containment Coupling in BDBA Condition Typical of the MASLWR

[+] Author Affiliations
F. Mascari, F. De Rosa, M. Polidori

ENEA, Bologna, Italy

A. M. Colletti, A. M. Costa, M. L. Richiusa, G. Vella

University of Palermo, Palermo, Italy

B. G. Woods

Oregon State University, Corvallis, OR

K. Welter

NuScale, Corvallis, OR

F. D’Auria

University of Pisa, Pisa, Italy

Paper No. SMR2014-3365, pp. V001T03A001; 11 pages
doi:10.1115/SMR2014-3365
From:
  • ASME 2014 Small Modular Reactors Symposium
  • ASME 2014 Small Modular Reactors Symposium
  • Washington, DC, USA, April 15–17, 2014
  • ISBN: 978-0-7918-4536-3
  • Copyright © 2014 by ASME

abstract

In the short term period the use of advanced Small Modular Reactor (SMR) is one of the most promising options for the deployment of nuclear technology. The validation and assessment of the best estimate thermal hydraulic system code TRACE against SMR thermal hydraulic phenomena is a novel effort. In this framework the use of the natural circulation database developed at the OSU-MASLWR test facility, simulating the MASLWR reactor prototype, is of interest for analyses of the TRACE code capability in predicting natural circulation and primary/containment coupled behavior in SMR. The target of this paper is to analyze the TRACE V5 capability for the simulation of natural circulation phenomena, at different primary and secondary side conditions, and to simulate the primary/containment coupling behavior, typical of the MASLWR design in Beyond Design-Basis Accidents (BDBA), by using a 3D TRACE model of the containment. The results of the calculated data show that the TRACE code is able to predict, from a quantitative point of view, the primary natural circulation mass flow rate, and that a 3D TRACE model of the containment is able to predict the main thermal hydraulic parameters, characterizing the primary/containment coupled thermal-hydraulic behavior.

Copyright © 2014 by ASME

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