Use of a Real-Time RELAP5 Model to Dynamically Test a Digital Feedwater Control System for a Boiling Water Reactor-Reference-Cited by-同舟云学术

Use of a Real-Time RELAP5 Model to Dynamically Test a Digital Feedwater Control System for a Boiling Water Reactor

Published:1995-08 Issue:2 Volume:111 Page:283-302
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Mowrey J. A.¹,Abdel-Khalik S. I.²,Ross K. W.³

Affiliation:

1. Foxboro Company, 33 Commercial Street Mail Code C412G, Foxboro, Massachusetts 02035

2. Georgia Institute of Technology George W. Woodruff School of Mechanical Engineering, Atlanta, Georgia 30332

3. Science Applications International Corporation 2109 Air Park Road S.E., Albuquerque, New Mexico 87106

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/NT95-A35138

Reference24 articles.

1. K. E. CARLSON et al. “RELAP5/MOD3 Code Manual Vol. I: Code Structure, System Models, and Solution Methods,” NUREG/CR-5535, EGG-2596, EG&G Idaho, Idaho National Engineering Laboratory (June 1990).

2. Conceptual Design Station Blackout and Loss-of-Flow Accident Analyses for the Advanced Neutron Source Reactor

3. Conceptual Design Loss-of-Coolant Accident Analysis for the Advanced Neutron Source Reactor

4. E. ELIAS et al. “Transient Simulation of ALWR Concepts Using RELAP5/MOD2,” 93-WA/HT-72, American Society of Mechanical Engineers (1993).

5. An Analysis of Feed-and-Bleed Cooling of a Pressurized Water Reactor

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