Workshop #1: Using FRI3D For Fire PRA Register Now

Wednesday, November 10, 2021 | 12:40-2:40 PM EST

Cost: $100 Workshop Only; $50 Full Meeting Paid Attendee

Description: The Fire Risk Investigation in 3D (FRI3D) software was initially developed as part of the research for enhanced fire analysis under Light Water Reactor Sustainability (LWRS) program. The goal of this software has two parts: (1) provide industry with a tool to simplify the process for developing and using detailed fire models; (2) provide a back-end for future enhanced fire analysis and possible extension to dynamic probabilistic risk analysis models. The FRI3D software was developed over the last two years to integrate 3D spatial modeling with existing fire probabilistic risk assessment (PRA) models and fire simulation codes.

Attendees will receive a certificate of attendance for these workshops.

Workshop #1 will be recorded and have access to the recorded presentations after the workshop.

Purpose of Workshop: Learn how to use FRI3D software to perform fire modeling and PRA. FRI3D encapsulates the fire and plant data into a unified database and simplifies the process with automated simulations using CFAST, THIEF, Heat Soak Methods. The workshop will serve as a guide to use FRI3D to perform Fire PRA and advanced fire modeling.

Presenter Bios: Ramprasad (Ram) Sampath is the founder and CEO of Centroid LAB an engineering software consultancy firm performing Advanced Visualization and Computational Dynamics and Simulations.

Steven Prescott, is a software analysis/integration engineer for the Risk Assessment and Management Services Department at Idaho National Laboratory. He specializes scientific and technical software design and development.

Workshop #2: Risk-informed Methodologies for Advanced Reactors: Needs, Challenges, and Case Study

Wednesday, November 10, 2021 | 12:40-4:10 PM EST

Cost: $100 Workshop Only; $50 Full Meeting Paid Attendee

Description: To facilitate the deployment of advanced nuclear power reactors, it is time-critical to focus on the risk-informed analysis of advanced reactors prior to, or in parallel with, technology developments. In recent years, there have been major efforts in the PRA developments for advanced reactors and its use in risk-informed decision-making, such as the Licensing Modernization Project (LMP), development of Title 10 of the Code of Federal Regulations, Part 53 (10CFR53) and other regulatory guidance by the Nuclear Regulatory Commission (NRC), as well as issuance of the ASME/ANS Non-LWR Probabilistic Risk Assessment Standard (RA-S-1.4-2021); however, there are still significant research needs for methodology developments. One of the key methodological challenges is that a design-specific experiential database is often limited or not available for advanced reactors, while the applicability and relevancy of the experiential data from the existing fleet to advanced reactors may be questionable due to differences in design principles, physical conditions, and operation and maintenance procedures. This workshop discusses the challenges and highlights possible research paths to alleviate them. As an example of the recent research activities, the methodological advancements and benchmark studies in an International Atomic Energy Agency (IAEA) Coordinated Research Project, “Methodology for Assessing Pipe Failure Rates in Advanced Water Cooled Reactors (WCRs),” are demonstrated. Based on the outcomes and insights from this IAEA project and other recent research activities, recommendations regarding the risk-informed analysis of advanced reactors are provided.

Attendees will receive a certificate of attendance for these workshops.

Purpose of Workshop: Identify the needs and methodological challenges in risk-informed analysis for advanced nuclear power reactors. Discuss research directions and paths to address those needs and challenges to facilitate the deployment of advanced reactors. As a case study, demonstrate the ongoing IAEA coordinated research project and provide recommendations.

This workshop will be led by the Socio-Technical Risk Analysis (SoTeRiA) Research Laboratory in the Department of Nuclear, Plasma, and Radiological Engineering at the University of Illinois at Urbana-Champaign.

Presenter Bios:

• Zahra Mohaghegh is an Associate Professor in the Department of Nuclear, Plasma, and Radiological Engineering in the Grainger College of Engineering at the University of Illinois Urbana-Champaign (UIUC). She established the Socio-Technical Risk Analysis (SoTeRiA) Research Laboratory (http://soteria.npre.illinois.edu/) at UIUC to advance risk science and applications for the safety of complex technological systems such as commercial nuclear power plants and advanced reactors. She has conducted research and published widely on probabilistic risk assessment, probabilistic physics of failure analysis, human-system reliability modeling, risk-informed decision making, and uncertainty analysis.
• Tatsuya Sakurahara is a Research Assistant Professor in the Department of Nuclear, Plasma, and Radiological Engineering in the Grainger College of Engineering at the University of Illinois Urbana-Champaign (UIUC). He is conducting research in the Socio-Technical Risk Analysis (SoTeRiA) Research Laboratory (http://soteria.npre.illinois.edu/) at UIUC to advance probabilistic risk assessment, focusing on probabilistic physics-of-failure analysis, maintenance work process modeling, uncertainty quantification, risk importance ranking, and common cause failure analysis.
• Bengt Lydell is the Owner/President of Sigma-Phase Inc. He has over 45 years of applied reliability and risk assessment experience. He specializes in probabilistic piping reliability analysis. In 2018-2022, he was the Chair of the IAEA Coordinated Research Project on “Methodology for Assessing Pipe Failure Rates in Advanced Water Cooled Reactors.”
• Klaus Heckmann works for Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH in Cologne/Germany, in the structural mechanics group. His professional interest is focused on leakage rates, fracture mechanics, probabilistic methods and techniques, and software development.
• Robertas Alzbutas is a Professor at the Kaunas University of Technology (KTU) and a Senior Research Associate at the Lithuanian Energy Institute (LEI). His research focus includes risk-informed inspection and decision-making, reduction of risk for leakage and rupture in nuclear piping, pipe rupture and inspection sensitivity analysis, and Bayesian analysis of heterogeneous reliability data.