Computational fluid dynamics and simulation-based-design approach for tight lattice nuclear fuel pin subassemblies

Hisashi Ninokata, Elia Merzari

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

6 Scopus citations

Abstract

This paper is a review of some of the recent achievement in computational fluid dynamics (CFD) being used or to be used in nuclear reactor thermal hydraulics analysis. We focus on the aspects of CFD that are most relevant to the tight lattice nuclear fuel pin subassemblies that are considered for future nuclear reactor core options, including those in light water reactors being aimed at a high burn-up or a long life core and, in general, sodium-cooled fast reactors. We will illustrate, in particular, turbulence phenomena that have been identified by CFD and peculiar to the flows in tight lattice nuclear fuel subassemblies, eccentric annuli and rectangular channels interconnected by a narrow gap. Highlighted phenomena include turbulence-driven secondary flows inside a subchannel, local turbulent-laminar transition in the narrow gap region between two adjacent fuel pins, and global pulsation of the flow across the length of a fuel subassembly. Special attention will be paid on linkage to the physics, limitation of the computational capability of the CFD methods, and the usefulness of the technology in reference to the foreseeable future.

Original languageEnglish (US)
Title of host publicationProceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12
StatePublished - Dec 1 2007
Event12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12 - Pittsburgh, PA, United States
Duration: Sep 30 2007Oct 4 2007

Publication series

NameProceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12

Other

Other12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12
CountryUnited States
CityPittsburgh, PA
Period9/30/0710/4/07

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering
  • Nuclear and High Energy Physics

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    Ninokata, H., & Merzari, E. (2007). Computational fluid dynamics and simulation-based-design approach for tight lattice nuclear fuel pin subassemblies. In Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12 (Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12).