Combining Insights from Probabilistic and Deterministic Safety Analyses in Option 4 from the IAEA Specific Safety Guide SSG-2-Reference-Cited by-同舟云学术

Combining Insights from Probabilistic and Deterministic Safety Analyses in Option 4 from the IAEA Specific Safety Guide SSG-2

Published:2014-10 Issue:1 Volume:188 Page:63-77
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Dusic Milorad¹,Dutton Mark²,Glaeser Horst³,Herb Joachim³,Hortal Javier⁴,Mendizábal Rafael⁴,Pelayo Fernando⁴

Affiliation:

1. International Atomic Energy Agency, Wagramerstrasse 5, A-1400 Vienna, Austria

2. Consultant, 85, Sycamore Crescent, Macclesfield, Cheshire, SK11 8LW, United Kingdom

3. Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH, Boltzmannstraβe 14, 85748 Garching, Germany

4. Consejo de Seguridad Nuclear (CSN), Justo Dorado 11, 28040 Madrid, Spain

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/NT13-16

Reference2 articles.

1. ANSI/ANS-51.1-1983, “Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants,” American Nuclear Society, La Grange Park, Illinois (1983)

2. KTA-SG-47 (Draft), “Zum Konzept: Klassifizierung von Ereignisablaufen fur die Auslegung von Kernkraftwerken,” Kerntechnischer Ausschuss (KTA), Salzgitter, Germany.

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