Modeling of Boiling Water Reactor Feedwater Control Algorithms
Author:
Affiliation:
1. Georgia Institute of Technology, G. W. Woodruff School of Mechanical Engineering Nuclear Engineering Program, Atlanta, Georgia 30332-0405
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-A2922
Reference14 articles.
1. K. E. CARLSON et al. “RELAP5/MOD3 Code Manual Volume 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, p. 1, American Society of Mechanical Engineers (1993).
5. An Analysis of Feed-and-Bleed Cooling of a Pressurized Water Reactor
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