The RETRAN-3D Code; Pressurized Water Reactor Multidimensional Neutron Kinetics Applications-Reference-Cited by-同舟云学术

The RETRAN-3D Code; Pressurized Water Reactor Multidimensional Neutron Kinetics Applications

Published:1998-05 Issue:2 Volume:122 Page:132-145
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Gose Garry C.¹,Shatford John G.¹,Agee Lance J.²

Affiliation:

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

2. Electric Power Research Institute 3412 Hillview Avenue, Palo Alto, California 94300

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/NT98-A2857

Reference10 articles.

1. Improved Pressurized Water Reactor Steamline Break Analysis Using RETRAN-02, ARROTTA, and VIPRE-02

2. J. H. McFADDEN, M. P. PAULSEN, G. C. GOSE, C. E. PETERSON, J. A. McCLURE, P. J. JENSEN, and J. L. WESTACOTT, “RETRAN-03—A Program for Transient Analysis of Complex Fluid Flow Systems, Volume 1: Theory and Numerics,” EPRI NP-7450, Electric Power Research Institute (May 1992).

3. L. D. EISENHART, “ARROTTA-01—Advanced Rapid Reactor Operational Transient Analysis Computer Code,” EPRI NP-7375, Electric Power Research Institute (Aug. 1993).

4. R. R. LEE, G. D. SEEBURGER, R. Q. HUYNH, G. B. SWINDLEHURST, D. M. ROWAN, D. E. BORTZ, R. VAN NAMEN, and P. A. GOODWIN, “Utility Implementation of EPRI Rod Ejection Accident Methodology,” EPRITR-100520, Electric Power Research Institute (Apr. 1992).

5. “Steam Line Break Methodologies—Simulation of PWR Steam Line Break Accidents—EPRI Sponsored Projects,” EPRI TR-100521, Electric Power Research Institute (Apr. 1992).

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