The RETRAN-03 Computer Code-Reference-Cited by-同舟云学术

The RETRAN-03 Computer Code

Published:1991-01 Issue:1 Volume:93 Page:105-115
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Paulsen M. P.¹,McFadden J. H.¹,Peterson C. E.¹,McClure J. A.¹,Gose G. C.¹,Jensen P. J.¹

Affiliation:

1. Computer Simulation & Analysis, Inc., P.O. Box 51596, Idaho Falls, Idaho 83405

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/NT91-A34522

Reference12 articles.

1. “A RETRAN Development Plan,” Electric Power Re-search Institute (Aug. 1986).

2. “A Plan for the Verification and Validation of the RETRAN-03 Computer Program,” Electric Power Research Institute (Apr. 1987).

3. V. CHEXAL and G. LELLOUCHE, “A Full-Range Drift-Flux Correlation for Vertical Flows,” NP-2989-SR, Rev. 1, Electric Power Research Institute (Sep. 1986).

4. S. W. BEYERLEIN, R. T. JACOBSEN, B. A. HARKINS, K. R. BJORIN, and W. P. CLARKE, “Short Equations of State for Use in RETRAN,” University of Idaho Report prepared for the Electric Power Research Institute (Dec. 1988).

5. J. H. McFADDEN et al. “RETRAN-02—A Program for Transient Thermal-Hydraulic Analysis of Complex Fluid Flow Systems,” EPRI-CCM-1850A, Rev. 4, Electric Power Research Institute (Nov. 1988).

Cited by 2 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. RETRAN-02 MOD5 and RETRAN-03 code benchmarks for Beaver Valley plant transients and FSAR analyses;Annals of Nuclear Energy;1995-05

2. A Nondiffusive Solution Method for RETRAN-03 Boiling Water Reactor Stability Analysis;Nuclear Technology;1992-11