CFD investigation of helical wire-wrapped 7-pin fuel bundle and the challenges in modeling full scale 217 pin bundle-Reference-Cited by-同舟云学术

CFD investigation of helical wire-wrapped 7-pin fuel bundle and the challenges in modeling full scale 217 pin bundle

Published:2007-12 Issue:24 Volume:237 Page:2332-2342
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Gajapathy R.,Velusamy K.,Selvaraj P.,Chellapandi P.,Chetal S.C.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference11 articles.

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3. Chen, B.C., Todreas, N.E., 1986. Prediction of coolant temperature field in a breeder reactor including interassembly heat transfer, COO-2245-20 TR, Rev. 1.

4. Hydraulic models and correlations for bare and wire-wrapped hexagonal rod bundles—bundle friction factors, sub-channel friction factors and mixing parameters;Chen;Nucl. Eng. Des.,1986

5. ‘Basic Equations of Engineering Science’, Schaum's Outline Series;Hughes,1964

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