Review and categorization of existing studies on the estimation of probabilistic failure metrics for Reactor Coolant Pressure Boundary piping and steam generator …

WC Cheng, T Sakurahara, S Zhang… - Progress in Nuclear …, 2020 - Elsevier
This paper presents the first output of the International Atomic Energy Agency (IAEA)
Coordinated Research Project (CRP), titled Methodology for Assessing Pipe Failure Rates …

An algorithm for enhancing spatiotemporal resolution of probabilistic risk assessment to address emergent safety concerns in nuclear power plants

H Bui, T Sakurahara, J Pence, S Reihani, E Kee… - Reliability Engineering & …, 2019 - Elsevier
Emergent safety concerns often involve complex spatiotemporal phenomena. In addressing
these concerns, the classical Probabilistic Risk Assessment (PRA) of Nuclear Power Plants …

GIS‐based integration of social vulnerability and level 3 probabilistic risk assessment to advance emergency preparedness, planning, and response for severe …

J Pence, I Miller, T Sakurahara, J Whitacre… - Risk …, 2019 - Wiley Online Library
In the nuclear power industry, Level 3 probabilistic risk assessment (PRA) is used to
estimate damage to public health and the environment if a severe accident leads to large …

Methodological and practical comparison of integrated probabilistic risk assessment (I-PRA) with the existing fire PRA of nuclear power plants

T Sakurahara, Z Mohaghegh, S Reihani… - Nuclear …, 2018 - Taylor & Francis
Nearly half of the US nuclear power plants (NPPs) are in the process of transitioning, or
have already transitioned, to a risk-informed, performance-based fire protection program …

[PDF][PDF] Modeling the interface of manual fire protection actions with fire progression in fire probabilistic risk assessment of nuclear power plants

T Sakurahara, Z Mohaghegh, S Reihani… - … Topical Meeting on …, 2017 - researchgate.net
This paper develops a methodology for “explcit” modeling of the interface between manual
fire protection (ie, manual fire detection and suppression) and a Computational Fluid …

Human reliability analysis-based method for manual fire suppression analysis in an integrated probabilistic risk assessment

T Sakurahara, Z Mohaghegh… - … -ASME Journal of …, 2020 - asmedigitalcollection.asme.org
Fire is one of the most critical initiating events that can lead to core damage in nuclear power
plants (NPPs). To evaluate the potential vulnerability of plants to fire hazards, fire …

[PDF][PDF] Human reliability analysis (HRA)-based method for manual fire suppression analysis in an integrated probabilistic risk assessment

T Sakurahara, S Reihani, E Kee… - ASCE-ASME J. Risk …, 2019 - researchgate.net
Fire is one of the most critical initiating events that can lead to core damage in Nuclear
Power Plants (NPPs). To evaluate the potential vulnerability of plants to fire hazards, Fire …

[PDF][PDF] Protective systems: Possible extensions to the roverd method

T Sakurahara, HB Hoang, J Pence… - Proc. Int. Topl. Mtg …, 2017 - researchgate.net
The Risk-informed Over Deterministic (RoverD) method1 has been developed to address a
specific US Nuclear Regulatory Commission (NRC) generic safety issue, Generic Safety …