VIPRE-02 Subchannel Validation against NUPEC BWR Void Fraction Data

Author:

Aounallah Yacine1,Coddington Paul1

Affiliation:

1. Paul Scherrer Institute, 5232 Villigen, PSI, Switzerland

Publisher

Informa UK Limited

Subject

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

Reference10 articles.

1. VIPRE-02—A Two-Fluid Thermal-Hydraulics Code for Reactor Core and Vessel Analysis: Mathematical Modeling and Solution Methods

2. C. W. STEWART, C. L. WHEELER, R. J. CENA, C. A. McMONAGLE, J. M. CUTA, and D. S. TRENT, “COBRA-IV-I: The Model and the Method,” BNWL-2214, Battelle-Pacific Northwest Laboratories (1977).

3. L. D. EISENHART, A. F. DIAS, J. L. WESTACOTT, T. J. DOWNAR, and H. G. JOO, “CORETRAN-01, Volume 1: Theory and Numerical Analysis, Draft,” WO-3574, Electric Power Research Institute (1997).

4. C. W. STEWART, J. M. CUTA, S. D. MONTGOMERY, J. M. KELLY, K. L. BASEHORE, T. L. GEORGE, and D. S. ROWE, “VIPRE-01: A Thermal-Hydraulic Analysis Code for Reactor Cores, Volume 1: Mathematical Modeling,” EPRI NP-2511-CCM, Electric Power Research Institute (1983).

5. J. M. CUTA, C. W. STEWART, A. S. KOONTZ, and S. D. MONTGOMERY, “VIPRE-01: A Thermal-Hydraulic Code for Reactor Cores, Volume 4: Applications,” NP-2511-CCMA, Electric Power Research Institute (1987).

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