RELAP5-3D

Versatile modeling and simulation tool to predict a nuclear reactor’s complex phenomena

Idaho National Laboratory’s RELAP5-3D is a robust modeling and simulation software designed to predict the intricate behavior of nuclear reactor systems. Originally developed in 1979, it has evolved beyond studying Light Water Reactors to successfully model the thermal and fluid performance of high-temperature gas-cooled reactors, super-critical CO2 reactors, sodium fast reactors, and molten salt reactors.

Accredited by international benchmarks and design bases analyses accepted by the Nuclear Regulatory Commission for reactor licensing, RELAP5-3D is recognized as the premier system analysis code. It is often the standard by which other system codes are measured.  RELAP5-3D has an extensive experiment database that validates the software’s modeling, offering confidence in predicting thermal and fluid performance.

With the ability to integrate into an analyst’s toolset, these codes provide a quick analysis of a system. When coupled with computational fluid dynamics (CFD) codes, such as openFOAM and STARCCM+, RELAP5-3D allows for comprehensive modeling.

RELAP5-3D is widely used for reactor safety analysis, design, operator training, and non-nuclear modeling and simulation.  The software is a Department of Energy 10 CFR 810 code, which means that RELAP5-3D is solely distributed through the INL Technology Deployment Office, which requires a license agreement, export control review, and approved use by the INL Code Oversight Group.

Meet our team

INL Thermal Fluid Systems Methods and Analysis focuses on non-nuclear experimental test beds and thermal hydraulic design and analysis using RELAP5 and MOOSE based tools.

RELAP5-3D in the News

Lab’s FY-23 licenses outnumber previous year

Idaho National Laboratory researchers love seeing their technologies at work in the marketplace, bolstering the nation’s economy, energy industry and communities.

Key nuclear modeling and simulation software releases new version

Idaho National Laboratory has released the latest version of RELAP5-3D, a versatile modeling and simulation tool that predicts complex phenomena happening inside a nuclear reactor. This update is the first RELAP5-3D code release in five years.

How INL’s reactor safety code extends beyond nuclear

A lot can change in 50 years. Just ask a carmaker, a telephone operator or any middle-aged adult. Like other creations from 1966, Idaho National Laboratory’s most successfully licensed invention — a reactor safety code — has evolved a lot since its inception.

Idaho National Laboratory
Paolo-Balestra

Dr. Paolo Balestra

Methods Lead for the Advanced Reactor Technology

Dr. Paolo Balestra obtained his master’s degree in energy engineering in 2012 and his Ph.D. in energy and environment with focus on nuclear engineering in 2017 at the “La Sapienza” University of Rome. He is currently the Methods Lead for the Advanced Reactor Technology - Gas Cooled Reactor (ART-GCR) DoE Program at the Idaho National Laboratory (INL). He is also work package manager of INL’s High Temperature Gas-cooled Reactor (HTGR) area of the multiphysics section of the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program. His research efforts are focused on two areas: the analysis and optimization of the new generation of advanced reactor design and the development and validation of dedicated advanced reactor designs simulation tools.

Dr. Victor Coppo Leite

Dr. Victor Coppo Leite

Researcher

Dr. Victor Coppo Leite is a researcher at Idaho National Laboratory who recently earned a Ph.D. in Nuclear Engineering from Pennsylvania State University. He also holds a Bachelor of Science and a Master of Science in the same field from the Federal University of Rio de Janeiro. His interests include incorporating machine learning methods into thermal hydraulic problems and multi-physics modeling. Currently, he applies his expertise to contribute to the development of RELAP5-3D, while also engaging in activities to maintain the code and conduct analyses.

Brandon Cox

Brandon Cox

Engineer & Software Developer

Brandon Cox is an engineer and software developer in the Thermal Fluid System Methods & Analysis Department at Idaho National Laboratory. In 2019 he graduated from Brigham Young University with a B.S. in Chemical Engineering. He has experience developing engineering software and computational fluid dynamics (CFD). He is currently a RELAP5-3D Developer and Analyst. In this capacity, he participates in various RELAP5-3D updates and development activities and corrects user errors. He also performs engineering calculations and analyses using RELAP5-3D and CFD. He has experience using Python, Fortran, Linux, and OpenFOAM. Outside of work he enjoys spending time with family and many outdoor activities including hiking, hunting, fishing, and photography.

Dr. Robert Kile

Dr. Robert Kile

Advanced Reactor Research and Development Engineer

Dr. Robert Kile is an Advanced Reactor Research and Development Engineer at Idaho National Laboratory. His work focuses on code validation for gas-cooled reactors. Dr. Kile is also the coordinator for the Depressurized Conduction Cooldown problem of the OECD-NEA HTTF Benchmark.

Dr. George Mesina

Dr. George Mesina

Acting manager for Thermal Fluids Systems, Methods & Analysis

Dr. George Mesina earned his PhD in Applied Mathematics in 1988 from the University of Pittsburgh. He has served as the RELAP5-3D Code Architect for 25 years. He is the acting manager for INL’s Thermal Fluids Systems, Methods, and Analysis department, responsible for the RELAP5-3D code analysts and developers and leading the RELAP program.

RELAP5 team portraits: Carlo Parisi

Dr. Carlo Parisi

Nuclear Engineer

Dr. Carlo Parisi holds a MSc and PhD in nuclear engineering from Pisa University, Italy. He joined INL in 2015, and since then he has worked on the Light Water Reactor Sustainability (LWRS) program, Versatile Test Reactor (VTR) and improved Advanced Test Reactor (ATR) concepts, and the sodium loop for the TREAT reactor. Since 2020 he is responsible for the thermal hydraulic design of the microreactor "MARVEL”.

connie stevens

Connie Stevens

Project Coordinator

Ms. Connie Stevens works as the RELAP5-3D project coordinator. She received a Master of Legal Studies from the University of Utah S.J. Quinney College of Law, and a B.Sc. in Applied Management from Brigham Young University-Idaho. Connie’s work is currently focused on building and strengthening relationships with domestic and international RELAP5-3D license holders, leading the organization of the annual International RELAP5 User Group (IRUG) meeting, and providing program management support to the department manager and RELAP5 team.

Dr. Mauricio Tano Retamales

Dr. Mauricio Tano Retamales

Staff Scientist

Dr. Mauricio Tano-Retamales is a Staff Scientist in the Thermal Fluids Systems and Methods Analysis group at Idaho National Laboratory (INL). He currently leads efforts for high- and intermediate-fidelity modeling and simulation of multiphysics phenomena in advanced nuclear reactors, which include the development of models coupling between neutronics, thermal-hydraulics, thermomechanics, salt chemistry, and corrosion. Additionally, Dr. Tano-Retamales is an active developer of INL’s coarse-mesh computational fluid dynamics (CFD) code Pronghorn and INL’s MOOSE-based subchannel code for advanced nuclear reactors. Dr. Tano-Retamales leads the coupling between RELAP5-3D and CFD codes and performs nuclear reactor analyses using RELAP5-3D.

Dr. Ishita Trivedi

Dr. Ishita Trivedi

Computational Scientist

Dr. Ishita Trivedi works as a computational scientist in the Advanced Reactor Design & Technology at Idaho National Laboratory (INL). She received her PhD in Nuclear Engineering from North Carolina State University focusing on Uncertainty Quantification and Propagation Methods for Safety Analysis of Lead-cooled Fast Reactors. Ishita also has a M.Sc. and B.Sc. in Nuclear Engineering from North Carolina State University and Pennsylvania State University, respectively. At INL, Ishita is involved in several advanced reactor multi-physics analysis projects including leading the MARVEL criticality benchmark development, nuclear thermal propulsion reactor modeling and simulation among other projects. Ishita also works in software quality assurance, validation & verification of INL applications.

Dr. Jan Vermaak

Dr. Jan Vermaak

Senior Nuclear Multiphysics Engineer

Jan Vermaak joined INL in 2022 as a Senior Nuclear Multiphysics Engineer. He has 14 years of diverse experience in reactor engineering ranging from nuclear safety analysis to managing reactor engineering at the Texas A&M University TRIGA reactor. He holds a bachelor’s degree in mechanical engineering and a master’s and PhD in nuclear engineering. Jan’s current work is focused on code development and analysis in the fields of neutronics, computational fluid dynamics (CFD), thermal-hydraulics, mechanical stress, and nuclear fuel performance.

Portrait: Piyush Sabharwall

Piyush Sabharwall

Irradiation Experiment Thermal Hydraulics Analysis Manager

Sabharwall is a distinguished staff scientist in the Nuclear Science and Technology directorate at the Idaho National Laboratory with more than 20 years of research and development experience. On June 24, 2024, he became manager of the department containing the RELAP5-3D program. He is a recognized expert in the design and safety of nuclear systems, with specialized knowledge in thermal-hydraulics, heat transfer, compact heat exchanger design and thermal energy systems. Sabharwall is the technical area lead on the U.S. Department of Energy Office of Nuclear Energy’s Microreactor R&D Program, the Holtec Small Modular Reactor 300 Advanced Reactor Demonstration Project and has led the development of a gas-cooled cartridge loop for the Versatile Test Reactor. In his current role as Thermal Fluid Systems Methods and Analysis department manager, he leads INL’s thermal hydraulics research supporting and guiding development of system code such as RELAP5, MOOSE-based tools such as SAM and Pronghorn, and leads the development of thermal-hydraulic validation experiments assisting with accelerated development and deployment of advanced reactor technologies. He has consulted for industries, both nationally and internationally, building technical expertise with an additional focus on market studies and economic viability to rebuild U.S. nuclear industrial infrastructure and position the U.S. industry to continue its leadership in the global energy market.