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

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

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

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