Monitoring Pressurized Water Reactor Transients Using Reactor Coolant Pumps-Reference-Cited by-同舟云学术

Monitoring Pressurized Water Reactor Transients Using Reactor Coolant Pumps

Published:1991-12 Issue:4 Volume:109 Page:325-340
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Adams James P.¹,McCreery Glenn E.¹,Kim Jong H.²

Affiliation:

1. Idaho National Engineering Laboratory, EG&G Idaho, Inc. P.O. Box 1625, Idaho Falls, Idaho 83415

2. Electric Power Research Institute, 3412 Hillview Avenue, Palo Alto, California 94304

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE91-A23858

Reference31 articles.

1. P. D. BAYLESS, “Experiment Results Report for LOFT Nuclear Experiments L3-5, L3-6, and L8-1,” EGG-LOFT-5471, EG&G Idaho, Inc. (July 1981).

2. J. P. ADAMS, P. D. BAYLESS, C. A. DOBBE and J. R. FINCKE, “Reactor Coolant Pump Trip Criteria and Transient Identification Technique for PWRs,” EPRI NP-5039, Electric Power Research Institute (Feb. 1987).

3. “NRC Integrated Program for the Resolution of Unresolved Safety Issues A-3, A-4, and A-5 Regarding Steam Generator Tube Integrity,” NUREG-0844, U.S. Nuclear Regulatory Commission (Apr. 1985).

4. J. J. MANZANORUIZ, “Experimental and Theoretical Study of Two-Phase Flow in Centrifugal Pumps,” PhD Dissertation, Massachusetts Institute of Technology (1980).

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