Development of dynamic fault tree model for reactor protection system-Reference-Cited by-同舟云学术

Development of dynamic fault tree model for reactor protection system

Published:2020-10-12 Issue:2 Volume:40 Page:
ISSN:1066-8527
Container-title:Process Safety Progress
language:en
Short-container-title:Proc Safety Prog

Author:

Fahmy Rania A.¹^ORCID

Affiliation:

1. Operational Safety and Human Factors Department Egyptian Nuclear and Radiological Regulatory Authority (ENRRA) Cairo Egypt

Publisher

Wiley

Subject

Safety, Risk, Reliability and Quality,General Chemical Engineering

Link

https://onlinelibrary.wiley.com/doi/pdf/10.1002/prs.12201

Reference20 articles.

1. U.S. Nuclear Regulatory Commission NRC Regulations Title 10 Code of Federal Regulations (10 CFR) appendix a to part 50—general design criteria for nuclear power plants;2011.

2. U.S. Nuclear Regulatory Commission Reliability study: Westinghouse reactor protection system 1984–1995. NUREG/CR‐5500 Volume 2;1998.

3. YamashitaM MiuraS FukudaM HiranoM. Reliability Analysis of Digital Reactor Protection System ASME International Conference on Nuclear Engineering. Presented at: 12th International Conference on Nuclear Engineering Volume 2 p.p 403–409;2004.

4. Safety assessment methodology for a digital reactor protection system;Lee D‐Y;Int J Control Autom Sys,2006

5. Tob R.Albuquerque1a Antonio C. F.Guimarães1bandMaria L.Moreira Event and fault tree model for reliability analysis of the Greek research reactor. Presented at: International Nuclear Atlantic Conference ‐ INAC 2013 Recife PE Brazil; November 24‐29 2013.

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