The Response of Ex-Core Neutron Detectors to Large- and Small-Break Loss-of-Coolant Accidents in Pressurized Water Reactors

Author:

Okyere E. Wilson1,Baratta Anthony J.2,Jester William A.2

Affiliation:

1. City University of New York-Staten Island, 130 Stuyvesant Place, Staten Island, New York 10301

2. The Pennsylvania State University, College of Engineering, Nuclear Engineering Department, 231 Sackett Building, University Park, Pennsylvania 16802

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference10 articles.

1. P. G. BAILEY, “A Review of Proposed Instrumentation for Measurement of Water Level as a Means of Detecting Inadequate Core Cooling in Pressurized Water Reactors,” EPRI NP-2727-SR, Electric Power Research Institute (1982).

2. “Analysis of Three Mile Island Unit-2 Accident,” NSAC-80-1, Rev. 1, Nuclear Safety Analysis Center (1980).

3. H. WARREN, L. BANDA, R. ANDERSON, L. OAKES, W. BENTLEY, A. BUHL, J. JONES, R. MONDAY, J. ROBINSON, and D. CAIN, “Interpretation of TMI-2 Instrument Data,” NSAC-28, Nuclear Safety Analysis Center (1982).

4. W. A. JESTER, A. J. BARATTA, J. EDWARDS, E. W. OKYERE, D. LOVE, and I. B. McMASTER, “A Concept for a Fast Neutron Non-Invasive Liquid Level and Density Gauge for Nuclear Reactor,” NUREG/CP 0041:3, U.S. Nuclear Regulatory Commission (1982).

5. C. L. NALEZNY, “Summary of NRC’s LOFT Program Experiments,” NUREG/CR-3214, U.S. Nuclear Regulatory Commission (1983).

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