A Noninvasive Technique for the Evaluation of Diversion Cross Flow at the Inlet of a Simulated Fuel Rod Bundle-Reference-Cited by-同舟云学术

A Noninvasive Technique for the Evaluation of Diversion Cross Flow at the Inlet of a Simulated Fuel Rod Bundle

Published:1988-03 Issue:3 Volume:80 Page:360-370
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Sedaghat Alireza¹,Castellana Frank S.²,Hsu Robert H.³,Macduff Robert B.⁴

Affiliation:

1. UColumbia University, Department of Applied Physics and Nuclear Engineering, New York, New York 10027

2. Squibb Diagnostics, Inc. P.O. Box 191, New Brunswick, New Jersey 08903

3. E.I. Du Pont de Nemours and Company, Inc. Savannah River Laboratory, Aiken, South Carolina 29808

4. Advanced Nuclear Fuels Corporation, P.O. Box 130, Richland, Washington 99352

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT88-A34060

Reference10 articles.

1. D. S. ROWE, “A Digital Computer Program for Steady State and Transient Thermal Hydraulics Analysis of Rod Bundle Nuclear Fuel Elements (COBRA IIIC),” BNWL-1695, Battelle Northwest Laboratory (1973).

2. R. W. BOWRING and J. LEVY, “Freon 7 Rod Cluster Subchannel Mixing Experiment,” AEEW-M906, Atomic Energy Authority Winfrith (May 1969).

3. D. S. ROWE and C. W. ANGLE, “Crossflow Mixing Between Parallel Flow Channels During Boiling—Computer Program for Coolant Boiling in Rod Arrays (COBRA I),” BNWL-371-Part I, Battelle Northwest Laboratory (1967).

4. R. T. LAHEY and B. S. SHIRALKAR, “Subchannel and Pressure Drop Measurement in a Nine-Rod Bundle for Diabatic and Adiabatic Conditions,” GEAP-13049, General Electric Company (Mar. 1970).

5. J. J. GINOUX, Two-Phase Flows and Heat Transfer with Application to Nuclear Reactor Design Problems, p. 30, Hemisphere Publishing Corp., New York (1978).

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