Realistic Small- and Intermediate-Break Loss-of-Coolant Accident Analysis Using WCOBRA/TRAC

Author:

Bajorek Stephen M.1,Petkov Nikolay2,Ohkawa Katsuhiro2,Kemper Robert M.2,Ginsberg Arthur P.3

Affiliation:

1. Kansas State University Department of Mechanical and Nuclear Engineering, Manhattan, Kansas 66506

2. Westinghouse Electric Company LLC, Nuclear Services Division P.O. Box 355, Pittsburgh, Pennsylvania 15230-0355

3. Consolidated Edison Company, Indian Point Unit 2 Broadway & Bleakly Avenues, Buchanan, New York 10511

Publisher

Informa UK Limited

Subject

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

Reference24 articles.

1. “Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors,” and Appendix K, “ECCS Evaluation Models,” Part 50, Section 50.46, Code of Federal Regulations (1992).

2. TECHNICAL PROGRAM GROUP, “Quantifying Reactor Safety Margins: Application of Code Scaling, Applicability, and Uncertainty Evaluation Methodology to a Large-Break Loss-of-Coolant Accident,” NUREG/CR-5249, EG&G Idaho (1989).

3. Application of code scaling applicability and uncertainty methodology to the large break loss of coolant

4. The role of the PIRT process in experiments, code development and code applications associated with reactor safety analysis

5. M. J. THURGOOD, J. M. KELLY, T. E. GUIDOTTI, R. J. KOHRT, and K. R. CROWELL, “COBRA/TRAC—AThermal-Hydraulic Code for Transient Analysis of Nuclear Reactor Vessels and Primary Coolant Systems,” NUREG/CR-3046, U.S. Nuclear Regulatory Commission (1983).

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