Some recent computations of rod bundle thermal hydraulics using boundary fitted coordinates

B. C.J. Chen, Surya Pratap Vanka, W. T. Sha

Research output: Contribution to journalArticle

Abstract

In this paper, we report the status of development of two computer codes for bench mark rod bundle thermal hydraulic analysis using the boundary-fitted coordinate method. A classification of the flow in rod bundles is made and details of two computer codes are given. The two codes solve essentially identical sets of conservation of mass, momentum and energy, but one of them treats the fully-elliptic set of equations, and the other neglects the axial diffusion of momentum and heat. The neglect of streamwise diffusion mades the flow partially-elliptic, and brings significant reductions in computer storage, and modest savings in required computer time. Results of some validation calculations are presented with applications to reactor geometries.

Original languageEnglish (US)
Pages (from-to)123-135
Number of pages13
JournalNuclear Engineering and Design
Volume62
Issue number1-3
DOIs
StatePublished - Dec 1980

Fingerprint

hydraulics
bundles
rods
Hydraulics
computer programs
momentum
seats
conservation
Momentum
reactors
heat
geometry
savings
Conservation
Geometry
Hot Temperature
energy
code

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Safety, Risk, Reliability and Quality
  • Waste Management and Disposal
  • Mechanical Engineering

Cite this

Some recent computations of rod bundle thermal hydraulics using boundary fitted coordinates. / Chen, B. C.J.; Vanka, Surya Pratap; Sha, W. T.

In: Nuclear Engineering and Design, Vol. 62, No. 1-3, 12.1980, p. 123-135.

Research output: Contribution to journalArticle

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