Methodologies for the Probabilistic Risk Assessment of Digital Reactor Protection and Control Systems-Reference-Cited by-同舟云学术

Methodologies for the Probabilistic Risk Assessment of Digital Reactor Protection and Control Systems

Published:2007-08 Issue:2 Volume:159 Page:167-191
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Aldemir Tunc¹,Miller Don W.¹,Stovsky Michael¹,Kirschenbaum Jason²,Bucci Paolo²,Mangan L. Anthony²,Fentiman Audeen¹,Arndt Steven A.³

Affiliation:

1. The Ohio State University, Department of Mechanical Engineering, 427 Scott Laboratory 201 West 19th Avenue, Columbus, Ohio 43210

2. The Ohio State University, Department of Computer Science and Engineering, 395 Dreese Labs 2015 Neil Avenue, Columbus, Ohio 43210

3. U.S. Nuclear Regulatory Commission, Two White Flint North, 11545 Rockville, Maryland 20852

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/NT07-A3863

Reference110 articles.

1. “Guideline for Performing Defense-in-Depth and Diversity Assessments for Digital I&C Upgrades—Applying Risk. Informed and Deterministic Methods,” EPRI-1002835, Electric Power Research Institute (2004).

2. T. ALDEMIR, D. W. MILLER, M. STOVSKY, J. KIRSCHENBAUM, P. BUCCI, A. W. FENTIMAN, and L. M. MANGAN, “Current State of Reliability Modeling Methodologies for Digital Systems and Their Acceptance Criteria for Nuclear Power Plant Assessments,” NUREG/CR-6901, U. S. Nuclear Regulatory Commission (2006).

3. “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,” NUREG-0800, U. S. Nuclear Regulatory Commission (1996).

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