An Overview of Nuclear Criticality Safety Analyses Performed to Support Three Mile Island Unit 2 Defueling-Reference-Cited by-同舟云学术

An Overview of Nuclear Criticality Safety Analyses Performed to Support Three Mile Island Unit 2 Defueling

Published:1989-12 Issue:4 Volume:87 Page:1134-1144
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Williams Daniel S.¹,Rommel John C.¹,Murray Raymond L.²

Affiliation:

1. Bechtel North American Power Corporation, 15740 Shady Grove Road Gaithersburg, Maryland 20877-1454

2. P.O. Box 5596, Raleigh, North Carolina 27650

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/NT89-A27705

Reference29 articles.

1. “Addition of Soluble and Insoluble Neutron Absorbers to the Reactor Coolant System of TMI-2,” GEND-26, U.S. Department of Energy (July 1984).

2. E. W. BARR, J. P. COLLETTI, J. A. EASLY and J. D. LUOMA, “TMI-2 Post Accident Criticality Analysis,” TDR-049, GPU Nuclear Corporation (Aug. 31, 1979).

3. R. M. WESTFALL, J. T. WEST, G. E. WHITESIDE and J. T. THOMAS, “Criticality Analysis of Disrupted Core Models of Three Mile Island Unit 2,” ORNL/CSD/TM-106, Oak Ridge National Laboratory (Dec. 1979).

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