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Advanced Reactor Safety (ARS)

Las Vegas, NV, June 16-19, 2024

  • Full Issue

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Page 0

  • Quantification of In-Containment Mechanistic Source Term for Advanced Light Water Reactor

    Yahya A. Alzahrani (NCSU), Mihai A. Diaconeasa (NCSU)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 4-15

  • An Assessment of the Applicability and Usability of Light Water Reactor Source Term Software for Non-Light Water Reactor Designers

    Matthew R. Denman (Kairos Power), Peiwen T. Whysall (Kairos Power), Jordan E. Hagaman (Kairos Power)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 16-24

  • The Development of Simplified Radionuclide Transport Code (SRT) Version 2.1

    Tyler Starkus (ANL), Dave Grabaskas (ANL), Dong Hoon Kam (ANL), Shayan Shahbazi (ANL)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 25-32

  • Consequence Uncertainty Quantification in LMP Applications

    Matthew Humberstone (U.S. Nuclear Regulatory Commission), Hanh Phan (U.S. Nuclear Regulatory Commission), Steven Unwin (PNNL), Steve Short (PNNL), Garill Coles (PNNL)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 33-41

  • Oxidation Model of the Accident Tolerant Fuel Implemented in NuScale Reactor Using MELCOR Code

    Mohammad Amer Allaf (Univ. Wisconsin, Madison), Grace Ejnik (Univ. Wisconsin, Madison), WooHyun Jung (Univ. Wisconsin, Madison), Michael Corradini (Univ. Wisconsin, Madison), Koroush Shirvan (MIT), Juliana Pacheco Duarte (Univ. Wisconsin, Madison)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 42-51

  • Digital Risk Analysis in Nuclear Engineering Projects: Designing for Safety, Performance, Reliability, and Security

    Shannon L. Eggers (INL), Robert W. Youngblood (INL)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 54-63

  • Integration of NIS (Nuclear Instrumentation Systems) with FPGA based RPS controls as a Seamless Safety Control System and Hardware Platform

    Tighe Smith (Paragon Energy Solutions), Lewis Wetzel (Paragon Energy Solutions)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 64-70

  • Consequence-Based Security for a Low Enriched UO2 Fueled Microreactor

    Jérémy Mangin (Ecole polytechnique), Koroush Shirvan (MIT), Jeong Ik Lee (KAIST), Neil Todreas (MIT)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 71-80

  • Implementing Multiple Control Paths in the Dual Error Propagation Graph for Stochastic Failure Analysis of Digital Instrumentation and Control Systems

    Arjun Earthperson (NCSU), Priyanka Pandit (NCSU), Mihai A. Diaconeasa (NCSU)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 81-90

  • Laying the Foundations for the Development of a Probabilistic Model Checking Method to Quantify Common Cause Failure Parameters in Digital Instrumentation and Control

    Priyanka Pandit (NCSU), Arjun Earthperson (NCSU), Mihai A. Diaconeasa (NCSU)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 91-99

  • The Co-Evolution of the GE-Hitachi BWRX-300 Probabilistic Safety Assessment and Plant Design

    Nathan DeKett (GE - Hitachi Nuclear Energy), Dennis Henneke (GE-Hitachi Nuclear Energy)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 106-114

  • Application of the GIF Safety Design Criteria and Safety Design Guidelines on Decay Heat Removal System to Next Generation Sodium-Cooled Fast Reactor in Japan

    Hidemasa Yamano (Japan Atomic Energy Agency), Satoshi Futagami (Japan Atomic Energy Agency), Koichi Higurashi (Mitsubishi FBR Systems, Inc.)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 115-124

  • Application of the RMPS+ Method to the BWRX-300 Isolation Condenser System: An Introduction

    Tyra Gordon (GE Hitachi Nuclear Energy), Nathan DeKett (GE Hitachi Nuclear Energy), Dennis Henneke (GE Hitachi Nuclear Energy), Jonathan Li (GE Hitachi Nuclear Energy)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 125-134

  • Development and Demonstration of a Prototype Molten Salt Sampling System

    Megan Harkema (Vanderbilt Univ.), Steven Krahn (Vanderbilt Univ.), Paul Marotta (Vanderbilt Univ.), Adam Burak (Univ. Michigan), Xiaodong Sun (Univ. Michigan), Piyush Sabharwall (INL)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 135-144

  • Application of the GIF Safety Design Criteria and Safety Design Guidelines on Reactor Shutdown System to Next Generation Sodium-Cooled Fast Reactor in Japan

    Hidemasa Yamano (Japan Atomic Energy Agency), Satoshi Futagami (Japan Atomic Energy Agency), Akihiro Shibata (Mitsubishi FBR Systems, Inc.)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 145-154

  • Leveraging Inverse Uncertainty Quantification to Enhance the Resilience of Nuclear Power Plant Construction Duration Estimation

    Priyanka Pandit (NCSU), Arjun Earthperson (NCSU), Mihai Diaconeasa (NCSU)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 156-165

  • Regulatory Treatment of Low Frequency External Events under a Risk-Informed Performance-Based Licensing Pathway: Enhanced SPRA-based Margins Assessment

    Ben Chen (ANL), David Grabaskas (ANL)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 166-175

  • Primary Site Selection for Air Freight Transport of Department of Defense Microreactors

    Thomas M. O'Connell (NCSU), Yahya A. Alzahrani (NCSU), Mihai A. Diaconeasa (NCSU)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 176-183

  • Protecting Microreactors from Extreme External Threats

    Amaury Le Person (MIT), Koroush Shirvan (MIT), Andrew Whittaker (Univ. Buffalo)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 184-193

  • Preliminary Study of Iodine Gas Removal in Sodium Pools

    Dong Hoon Kam (ANL), David Grabaskas (ANL), Yasushi Okano (Japan Atomic Energy Agency), Akihiro Uchibori (Japan Atomic Energy Agency), Tyler Starkus (ANL), Matthew Bucknor (ANL)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 196-207

  • Thermochemical Modeling of Radionuclide Vapor-Liquid Equilibria in Sodium Pools for SFR Mechanistic Source Term Analysis

    Shayan Shahbazi (ANL), Sara Thomas (ANL), Tyler Starkus (ANL), David Grabaskas (ANL)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 208-217

  • A Mass Transfer Model for Source Term Release from A Spilled Molten Salt Pool Accounting for Both Gas and Liquid Side Resistances

    Quan Zhou (Kairos Power), Kyoung Min Kang (Kairos Power), Jake McMurray (Kairos Power), Matthew Denman (Kairos Power), Haihua Zhao (Kairos Power)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 218-226

  • Thermodynamic Analysis of the Relationship between Peak Fuel Enthalpy and Fuel Behavior for Fast Reactor Design

    Yan Peng (China Institute of Atomic Energy)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 227-236

  • Risk-Informed and Performance-Based Approaches to Safety Analysis and Classification for Microreactors

    Alan Smith (Oklo Inc.), Patrick Everett (Oklo Inc.), Kellen McCarroll (Oklo Inc.), Alex Renner (Oklo Inc.)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 238-247

  • Application of a Qualitative Risk-Informed, Performance-Based Approach for the MARVEL Microreactor at the Idaho National Laboratory

    Doug Gerstner (INL), Jason Andrus (INL), Amanda Foley (INL), Troy Reiss (INL)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 248-257

  • Reducing the Maintenance Cost of Advanced Nuclear Reactors under Risk Constraints through Condition Monitoring, Probabilistic Risk Assessment, and Maintenance Optimization

    Yunfei Zhao (Univ. Maryland)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 258-267

  • Addressing Uncertainties Across All Design Stages of Advanced Reactors Development

    Rawan Mustafa (NCSU), Mostafa Hamza (NCSU), Yahya A. Alzahrani (NCSU), Mihai A. Diaconeasa (NCSU)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 268-277

  • Risk Informed Material Categorization

    Brian Kloiber (Oklo Inc.)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 278-287

  • Literature Review of Preliminary Initiating Events for a Gas-Cooled Fast Reactor Conceptual Design

    Steven Krahn (Vanderbilt Univ.), Megan Harkema (Vanderbilt Univ.), Irfan Ibrahim (Vanderbilt Univ.), Hangbok Choi (General Atomics), John Bolin (General Atomics), Eric Thornsbury (EPRI)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 290-299

  • On the Applicability of the General Transient Initiating Event Group for Advanced Reactors

    Mostafa Hamza (NCSU), Huafei Liao (X-energy), Mark Cursey (Jensen Hughes), Karl Fleming (Technology Insights), Mihai A. Diaconeasa (NCSU)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 300-309

  • The State of Art of the Human Failure Events Dependency Analysis Methods

    Mostafa Hamza (NCSU), Mihai A. Diaconeasa (NCSU)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 310-318

  • Management of Risks Associated with Application of Novel Materials in Novel Operating Environments in Novel Reactor Designs

    R. Youngblood (INL), S. Ferrara (INL)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 319-328

  • Risk Metrics for Advanced Reactors

    Eric Thornsbury (EPRI), Stephen Hess (Jensen Hughes), Jeffrey Julius (Jensen Hughes), Chloe Howard (Jensen Hughes)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 329-337

  • Integrating PRA into the Conceptual and Preliminary Design Phases of an Advanced Reactor Project

    Thomas Morgan (Enercon Services), Dennis Henneke (GE Hitachi), Jonathan Li (GE Hitachi), Raymond Dremel (GE Hitachi)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 340-347

  • Some Special Topics for the SMR Emergency Planning

    Dan Serbanescu (Group of Risk Analyses GLERUNR), Petre Min (Group of Risk Analyses GLERUNR)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 348-357

  • Aalo Atomics' High Level Licensing Strategy

    Asmaa S. Farag (NCSU), Amir Afzali (Aalo Atomics), Yasir Arafat (Aalo Atomics), Matt Loszak (Aalo Atomics), Arjun Earthperson (NCSU), Mihai A. Diaconeasa (NCSU)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 358-365

  • Licensing Advanced Reactor Designs: Leveraging Operating History to Develop Creative Solutions in Addressing Future Focus Areas

    Qin Pan (Nuclear Regulatory Commission), Sunil D. Weerakkody (Nuclear Regulatory Commission)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 366-375

  • Insights from Multi-Unit Level 1, 2 and 3 Probabilistic Risk Assessment Results for Light-Water Reactor Designs - What Can Be Extrapolated to Advanced Reactor Designs?

    Susan E. Cooper (US Nuclear Regulatory Commission), Erick Ball (US Nuclear Regulatory Commission), Trey Hathaway (US Nuclear Regulatory Commision), Keith Compton (US Nuclear Regulatory Commission), Selim Sancaktar (Retired), Alan Kuritzky (US Nuclear Regulatory Commission), Latonia Enos-Sylla (US Nuclear Regulatory Commission)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 376-386

  • Improving the Efficiency of Dynamic Probabilistic Risk Assessment with Monte Carlo Tree Search and Importance Sampling

    Joseph O'Leary (Univ. Maryland), Yunfei Zhao (Univ. Maryland)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 390-399

  • Towards a Deep-Learning based Heuristic for Optimal Variable Ordering in Binary Decision Diagrams to Support Fault Tree Analysis

    Arjun Earthperson (NCSU), Egemen M. Aras (NCSU), Asmaa A. Farag (NCSU), Mihai A. Diaconeasa (NCSU)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 400-409

  • Quantifying Safety System Unavailability Margins via Inverse Estimation of Event Sequence Frequencies

    Arjun Earthperson (NCSU), Priyanka M. Pandit (NCSU), Mihai A. Diaconeasa (NCSU)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 410-419

  • Markov Decision Processes for Intelligent, Risk-Informed Asset-Management Decision-Making

    David Grabaskas (ANL), Yunfei Zhao (Ohio State), Carol Smidts (Ohio State), Vera Moiseytseva (ANL), Roberto Ponciroli (ANL), Pascal Brocheny (Framatome)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 420-429

  • Data Updating Model Development with Bayesian Inference for Data Analysis for Probabilistic Risk Assessment Application

    Joomyung Lee (NCSU), Rawan Mustafa (NCSU), Mostafa Hamza (NCSU), Olivier Retourne (X-energy), Huafei Liao (X-energy), Glen Lawson (X-energy), Mihai A. Diaconeasa (NCSU)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 430-438

  • Comparison of Point Kinetics and Spatial Kinetics Models for the Generic Fluoride-Salt-Cooled High-Temperature Reactor (gFHR)

    Jonathan L. Barthle (Univ. Tennessee, Knoxville), Edward M. Duchnowski (Univ. Tennessee, Knoxville), Nicholas R. Brown (Univ. Tennessee, Knoxville)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 440-449

  • LES at Low Richardson Number to investigate Thermal Stratification in SFRs Upper Plenums

    Theodore Chu (Virginia Commonwealth Univ.), Trevor Franklin (Virginia Commonwealth Univ.), L.B. Carasik (Virginia Commonwealth Univ.)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 450-459

  • SAS4A/SASSYS-1 Modeling Improvements for the Transition to Natural Circulation

    Rachel A. Thomas (ANL), Daniel J. O'Grady (ANL), Thomas H. Fanning (ANL), Acacia J. Brunett (ANL)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 460-469

  • Automated Multiphysics Evaluation Model Assessment and Determination of Thermal-Hydraulic Safety Margins

    Clyde Huibregtse (Oklo), Amrit Patel (Oklo), Patrick Everett (Oklo)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 470-479

  • Mechanical Aerosol Generation from Two-Phase Flow Pipe Breaks for Low Pressure FHR

    Kyoung M. Kang (Kairos Power), Quan Zhou (Kairos Power), Matthew Denman (Kairos Power), Timothy Drzewiecki (Kairos Power)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 482-491

  • An Examination of Sodium Aerosol Behavior Based on Available Experimental Data

    Tyler Starkus (ANL), Dave Grabaskas (ANL), Dong Hoon Kam (ANL), Shayan Shahbazi (ANL)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 492-499

  • Modeling Radionuclide Inventories in MSR Off-Gas Systems with Radiochemical Transport Analysis

    Shayan Shahbazi (ANL), Samuel Walker (INL), Mauricio Tano (INL), Tingzhou Fei (ANL), Yan Cao (ANL), David Grabaskas (ANL)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 500-509

  • Implementation of the Sourdough Fuel Cycle and Waste Management Strategy in the EIRENE Novel Molten Salt Reactor Design

    C. Erika Moss (Univ. Tennessee, Knoxville), Ondrej Chvala (Univ. Tennessee, Knoxville), Donny Hartanto (ORNL), John P. Carter (INL)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 510-519

  • Advancements in Depletion Modeling for Molten Salt Reactors Using OpenMC: A Case Study with the MSRE

    Lorenzo Chierici (Copenhagen Atomics), Erik Bergbäck Knudsen (Copenhagen Atomics)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 520-529

  • Advancing SAPHIRE: Transitioning from Legacy to State-of-Art Excellence

    Stephen T. Wood (INL), Jordan T. Boyce (INL), Egemen M. Aras (NCSU), Asmaa S. Farag (NCSU), Mihai A. Diaconeasa (NCSU)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 532-541

  • Enhancing the SAPHIRE Solve Engine: Initial Progress and Efforts

    Egemen M. Aras (NCSU), Stephen T. Wood (INL), Jordan T. Boyce (INL), Asmaa S. Farag (NCSU), Mihai A. Diaconeasa (NCSU)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 542-551

  • Introducing OpenPRA's Quantification Engine: Exploring Capabilities, Recognizing Limitations, and Charting the Path to Enhancement

    Egemen M. Aras (NCSU), Arjun Earthperson (NCSU), Hasibul H. Rasheeq (NCSU), Asmaa S. Farag (NCSU), Stephen T. Wood (INL), Jordan T. Boyce (INL), Mihai A. Diaconeasa (NCSU)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 552-561

  • OpenMHA: Open-Source Code for Creating Multi-Hazards Logic and Area PRA Models Considering Aging of SSCs

    Akram S. Batikh (NCSU), Mihai A. Diaconeasa (NCSU)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 562-572

  • Evaluating PRA Tools for Accurate and Efficient Quantifications: A Follow-Up Benchmarking Study Including FTREX

    Asmaa Farag (NCSU), S. Ted Wood (INL), Arjun Earthperson (NCSU), Egemen M. Aras (INL), Jordan T. Boyce (INL), Mihai A. Diaconeasa (NCSU)

    Proceedings | Advanced Reactor Safety (ARS) | Las Vegas, NV, June 16-19, 2024 | Pages 573-582

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