Probabilistic safety assessment of portable equipment applied in VVER-1000/V446 nuclear reactor during loss of ultimate heat sink accident for stress test program development

• Published in: Progress in nuclear energy (New series) Vol. 117; p. 103101
• Main Authors: Tabadar, Z., Ansarifar, G.R., Pirouzmand, A.
• Format: Journal Article
• Language: English
• Published: Oxford Elsevier Ltd 01.11.2019; Elsevier BV
• Subjects: Aircraft accidents; Blackout; Boilers; Core damage frequency; Damage assessment; Demineralizing; Diesel fuels; Earthquake damage; Fault trees; Flooding; FusselVesely importance measure; Heat sinks; Loss of ultimate heat sink; Nuclear accidents; Nuclear accidents & safety; Nuclear engineering; Nuclear fuels; Nuclear power plants; Nuclear reactors; Nuclear safety; Portable equipment; Probabilistic safety assessment; Probability; Pumps; Seismic engineering; Spent nuclear fuels; Stress test program; Terrorism; VVER-1000 nuclear reactor; Fukushima Japan; Probabilistic safety assessment; Loss of ultimate heat sink; FusselVesely importance measure; Stress test program; Core damage frequency; Portable equipment; VVER-1000 nuclear reactor

After the Fukushima Daiichi nuclear accident, all EU nuclear power plants became subject to safety assessments as stress test programs. The objective was to check and improve the capability of nuclear safety systems in withstanding damage from hazards caused by flooding, earthquakes, terrorist attac...