VIPRE-02—A Two-Fluid Thermal-Hydraulics Code for Reactor Core and Vessel Analysis: Mathematical Modeling and Solution Methods-Reference-Cited by-同舟云学术

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

Published:1992-11 Issue:2 Volume:100 Page:246-259
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Kelly Joseph M.¹,Stewart Charles W.¹,Cuta Judith M.¹

Affiliation:

1. Battelle Pacific Northwest Laboratories, P.O. Box 999, 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/NT92-A34746

Reference10 articles.

1. 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 Code for Reactor Cores,” NP-2511, Vols. 1-5, Rev. 3, Electric Power Research Institute (Aug. 1989).

2. M. J. THURGOOD and T. L. GEORGE, “COBRA/TRAC-A Thermal-Hydraulics Code for Transient Analysis of Nuclear Reactor Vessels and Primary Coolant Systems,” NUREG/CR-3046, U.S. Nuclear Regulatory Commission (1982).

3. C. L. WHEELER, M. J. THURGOOD, T. E. GUIDOTTI, and D. E. DeBELLIS, “COBRA-NC: A Thermal-Hydraulic Code for Transient Analysis of Nuclear Reactor Components,” NUREG/CR-3262, U.S. Nuclear Regulatory Commission (1986).

4. J. H. STUHMILLER, “Implementation of the Dynamic Flow Regime Model in Thermal-Hydraulic Codes,” Final Report on RP-2806-1, Electric Power Research Institute (July 1987).

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