The THYC Three-Dimensional Thermal-Hydraulic Code for Rod Bundles: Recent Developments and Validation Tests-Reference-Cited by-同舟云学术

The THYC Three-Dimensional Thermal-Hydraulic Code for Rod Bundles: Recent Developments and Validation Tests

Published:1995-12 Issue:3 Volume:112 Page:331-345
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Aubry Sylvie¹,Caremoli Christian²,Olive Jean¹,Rascle Paul²

Affiliation:

1. Electricité de France, DER/RNE Ecole Centrale des Arts et Manufactures Heat Transfer and Aerodynamics Department 6, quai Watier, 78401 Chatou Cedex, France

2. Electricité de France, DER/RNE Ecole Centrale des Arts et Manufactures, Reactor Physics Department 1, Avenue du General de Gaulle, 92140 Clamart, France

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/NT95-A35159

Reference5 articles.

1. The Three-Dimensional Time and Volume Averaged Conservation Equations of Two-Phase Flow

2. S. K. CHENG and N. E. TODREAS, “Constitutive Correlations for Wire Wrapped Subchannel Analysis Under Forced and Mixed Convection Conditions,” DOE/ET: 37240.108 TR, Massachusetts Institute of Technology (1984).

3. The development of a model for three-dimensional flow in tube bundles

4. C. F. FIGHETTI and D. G. REDDY, “Parametric Study of CHF Data,” EPRI-NP2609, Columbia University (Sep. 1989).

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