Machine learning of fire hazard model simulations for use in probabilistic safety assessments at nuclear power plants

C Worrell, L Luangkesorn, J Haight… - Reliability Engineering & …, 2019 - Elsevier
This study explored the application of machine learning to generate metamodel
approximations of a physics-based fire hazard model. The motivation to generate accurate …

Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions

T Barani, G Pastore, D Pizzocri, DA Andersson… - Journal of Nuclear …, 2019 - Elsevier
In this work, we present a model of fission gas behavior in U 3 Si 2 under light water reactor
(LWR) conditions for application in engineering fuel performance codes. The model includes …

Risk-informed safety analysis for accident tolerant fuels

C Parisi, Z Ma, D Mandelli, N Anderson… - Nuclear Science and …, 2020 - Taylor & Francis
Accident tolerant fuels (ATFs) are being tested by different nuclear vendors and research
organizations, and their introduction into the US light water reactor fleet is planned for the …

Hydraulic behavior of fault zones in pump tests of geothermal wells: a parametric analysis using numerical simulations for the Upper Jurassic aquifer of the North …

F Konrad, A Savvatis, F Wellmann, K Zosseder - Geothermal Energy, 2019 - Springer
Fault zones in the Upper Jurassic aquifer of the North Alpine Foreland Basin are generally
regions with possibly increased hydraulic properties. They are consequently often part of the …

Preliminary sensitivity analysis for an ex-vessel LOCA without plasma shutdown for the EU DEMO WCLL blanket concept

M D'Onorio, F Giannetti, MT Porfiri, G Caruso - Fusion Engineering and …, 2020 - Elsevier
In this early development phase of the DEMO design the uncertainty affecting many
operational and design parameters can modify main outcomes of accident scenario aiming …

Measuring risk-importance in a Dynamic PRA framework

D Mandelli, Z Ma, C Parisi, A Alfonsi, C Smith - Annals of Nuclear Energy, 2019 - Elsevier
Abstract Risk Importance Measures (RIMs) are indexes that are used to rank Structures,
Systems, and Components (SSCs). The most used measures are: Risk Reduction Worth …

Plant-level scenario-based risk analysis for enhanced resilient PWR–SBO and LBLOCA

Z Ma, C Parisi, H Zhang, D Mandelli, C Blakely, J Yu… - 2018 - osti.gov
This report documents the activities performed during the FY2018 for the DOE Light Water
Reactor Sustainability (LWRS) Program, Risk-Informed System Analysis (RISA) Pathway …

Development of a dynamic event tree (DET) to analyze SBO accident in VVER-1000/V446 nuclear reactor

ME Amirsoltani, A Pirouzmand… - Annals of Nuclear Energy, 2022 - Elsevier
Probabilistic safety assessment (PSA) is the main approach currently applied in safety
assessment of nuclear power plants to calculate the core damage frequency (CDF). The …

Uncertainty quantification method for RELAP5-3D© using RAVEN and application on NACIE experiments

V Narcisi, P Lorusso, F Giannetti, A Alfonsi… - Annals of Nuclear …, 2019 - Elsevier
The best estimate plus uncertainty (BEPU) method plays a key role in the development of
the innovative Generation IV nuclear reactors, for the improvement of knowledge and the …

Risk-Informed Analysis for an Enhanced Resilient PWR with ATF, FLEX, and Passive Cooling

Z Ma, C Parisi, CB Davis, RL Boring PhD, H Zhang… - 2019 - osti.gov
This report documents the activities performed by Idaho National Laboratory (INL) during the
fiscal year (FY) 2019 for the DOE Light Water Reactor Sustainability (LWRS) Program, Risk …