Two-fluid model of two-phase flow in a pin bundle of a nuclear reactor-Reference-Cited by-同舟云学术

Two-fluid model of two-phase flow in a pin bundle of a nuclear reactor

Published:1980-07 Issue:7 Volume:23 Page:991-1001
ISSN:0017-9310
Container-title:International Journal of Heat and Mass Transfer
language:en
Short-container-title:International Journal of Heat and Mass Transfer

Author:

Chawla T.C.,Ishii M.

Publisher

Elsevier BV

Subject

Fluid Flow and Transfer Processes,Mechanical Engineering,Condensed Matter Physics

Reference25 articles.

1. Equations of motion for twophase flow in a pin bundle of a nuclear reactor;Chawla;Int. J. Heat Mass Transfer,1978

2. COBRA-IV : the model and the method;Stewart;Battelle Pacific Northwest Laboratory Report BNWL-2214, NRC-4,1977

3. A mathematical model for transient subchannel analysis of rod-bundle nuclear fuel elements;Rowe;J. Heat Transfer,1973

4. HAMBO, a computer programme for the subchannel analysis of the hydraulic and burnout characteristics of rod clusters — I;Bowring;General description, United Kingdom Atomic Energy Authority Report AEEW-R524,1967

5. SASS Code 1, subchannel analysis for the steady state;Pierre;Atomic Energy of Canada Limited Report AECL-APPE-41,1966

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