On the numerical simulation of thermal striping in the upper plenum of a fast reactor

E. Merzari, W. D. Pointer, A. Obabko, P. Fischer

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

The structures present in the upper plenum of a sodium cooled fast reactor are potentially subject to thermal striping. In fact there is the possibility of a significant temperature variation at the exit of two adjacent subassemblies since they are typically hydro-dynamically isolated in a SFR core. It has been demonstrated over the years that it is extremely difficult to produce generalized heuristic models for the prediction of thermal striping due to the inherent dependency of such phenomena upon the geometry and local flow conditions. Thus the development and validation of numerical tools such CFD to predict thermal striping is crucial for safety evaluation. Thermal striping is however very challenging for CFD due to the presence of buoyancy effects and turbulent mixing, which usually require a separate treatment to achieve satisfying results. Fundamental experiments targeted specifically to CFD validation are thus necessary to select the appropriate models and methodologies for the simulation offlows involving thermal striping. The present work is concerned with steady-state and unsteady CFD simulations of an experiment currently scheduled to be performed at Argonne National Laboratory. The test section will be instrumented with particle image velocimetry (PIV) capable of extracting instantaneous velocity distributions over any given cross section in the domain and with a high-speed thermal imaging camera that will provide real-time temperature distributions on the upper surface of the test section. When operational, data from the MAX experiment will be compared with LES and RANS simulations. The calculations presented in this work were performed in support of the experiment definition and development. In particular the focus will be on the apparent strong sensitivity of the numerical results upon the modeling of the jet inlets.

Original languageEnglish (US)
Title of host publicationInternational Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010
Pages595-603
Number of pages9
StatePublished - Sep 7 2010
Externally publishedYes
EventInternational Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010 - San Diego, CA, United States
Duration: Jun 13 2010Jun 17 2010

Publication series

NameInternational Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010
Volume1

Other

OtherInternational Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010
CountryUnited States
CitySan Diego, CA
Period6/13/106/17/10

ASJC Scopus subject areas

  • Energy Engineering and Power Technology
  • Nuclear Energy and Engineering

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    Merzari, E., Pointer, W. D., Obabko, A., & Fischer, P. (2010). On the numerical simulation of thermal striping in the upper plenum of a fast reactor. In International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010 (pp. 595-603). (International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010; Vol. 1).