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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Dec 2024
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Nuclear Science and Engineering
January 2025
Nuclear Technology
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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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
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