Spanish contribution to the development and application of probabilistic safety analysis: Experience and future challenges-Reference-Cited by-同舟云学术

Spanish contribution to the development and application of probabilistic safety analysis: Experience and future challenges

Published:2024-03 Issue: Volume:418 Page:112879
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Martorell S.,Martón I.,Sánchez A.,Courtin S.,Queral C.,Meléndez E.,Olivar F.,García-Zamorano A.,Marín R.,Díaz P.,Serrano A.,Rísquez A.,Gonzalez B.,Saiz M.,Aramayo C.,Paris C.,Herrero R.,Martín-Valdepeñas J.M.,Gil B.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference98 articles.

1. American Society of Mechanical Engineers, ASME (2013). ASME/ANS RA-Sb-2013, Addenda to ASME/ANS RA-S-2008 Standard for Level 1 / Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications, September 2013. [44] Electric Power Research Institute, EPRI (2014b). The EPRI HRA Calculator® Version 5.1 Software Manual, May 2014.

2. American Society of Mechanical Engineers, ASME (2013b). Boiler and Pressure Vessel Code, Section XI, “Rules for Inservice Inspection of Nuclear Power Plant Components”.

3. American Society of Mechanical Engineers, ASME (2017). ASME OM-2017. Operation and Maintenance of Nuclear Power Plants. May 2017.

4. Addenda to ASME/ANS RA-S-2008, Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications;American Society of Mechanical Engineers, ASME,2009

5. Particle Swarm Optimization of safety components and systems of nuclear power plants under uncertain maintenance planning;Carlos;Adv. Eng. Software,2002