Features of the RETRAN-03 Computer Code-Reference-Cited by-同舟云学术

Features of the RETRAN-03 Computer Code

Published:1988-12 Issue:3 Volume:83 Page:274-288
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Paulsen M. P.¹,Griebenow B. E.¹,Feinauer L. R.¹,McFadden J. H.¹,Jensen Peter J.¹

Affiliation:

1. EI International, Inc. P.O. Box 736, One Energy Drive, Idaho Falls, Idaho 83401

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-A34141

Reference9 articles.

1. “A RETRAN-03 Development Plan,” Electric Power Research Institute, Nuclear Power Division (Aug. 1986).

2. B. CHEXAL and G. LELLOUCHE, “A Full-Range Drift-Flux Correlation for Vertical Flows,” EPRI-NP-3989-SR, Rev. 1, Electric Power Research Institute (Sep. 1986).

3. J. H. McFADDEN, R. E. NARUM, C. E. PETERSON, C. NOBLE, R. F. FARMAN, J. A. McCLURE, M. P. PAULSEN, K. D. RICHERT, E. D. HUGHES, G. C. GOSE, L. V. ELLIS, N. L. ELLIS, K. R. KATSMA, C. G. MOTLOCH, G. C. RICE and D. S. TROTT, “RETRAN-02—A Program for Transient Thermal-Hydraulic Analysis of Complex Fluid Flow Systems,” EPRI-CCM-1850A, Rev. 4, Electric Power Research Institute (July 1987).

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

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