ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Oak Ridge community roundtable explores workforce challenges
Federal and contractor officials, community leaders, and educators gathered in Knoxville, Tenn., on October 29 for a roundtable event focused on ensuring the Oak Ridge Office of Environmental Management (OREM) and its partners have the resources and infrastructure needed to support a robust, talented workforce in the years ahead.
March 15, 2024|11:00AM–12:30PM (12:00–1:30PM EDT)
Available to All Users
The nuclear industry has seen a constant increase in the past few years for the design and development of small modular and micro-reactors, computational capability, and international collaboration. The American Nuclear Society's leaders in nuclear thermal hydraulics have been at the forefront of these efforts. This webinar hosted by the Thermal Hydraulics Division highlights some of the most impactful work from 2023 that contributes to the international nuclear thermal hydraulic stage.
Panelists
April NovakAssistant Professor, Nuclear, Plasma, and Radiological Department, University of Illinois at Urbana-Champaign
Xu WuAssistant Professor of Nuclear Engineering, North Carolina State University
Kevin ZwijsenResearch Consultant, Nuclear Research and Consultancy Group
Moderator
Marilyn DelgadoMechanical System Design Engineer, Advanced Technologies Division, BWX Technologies
Biographies
Marilyn Delgado
Marilyn is a Mechanical System Design Engineer with the Advanced Technologies Division of BWX Technologies. She works on the design, analysis, testing, and prototype development of high-temperature gas micro-reactors and micro-reactor plants. Prior to joining BWXT, she graduated with her Bachelors of Mechanical Engineering from The City College of New York in 2015, Masters in Nuclear Engineering from Texas A&M University in 2018, and PhD in Interdisciplinary Engineering from Texas A&M University in 2021 combining Nuclear and Mechanical Engineering Disciplines. Her research and dissertation work focused on experimental studies of flow induced vibration and vortex shedding phenomena in advanced nuclear heat exchanger designs.
April Novak
April is an Assistant Professor in the Nuclear, Plasma, and Radiological (NPRE) Department at the University of Illinois at Urbana-Champaign (UIUC), where she leads research programs in computational methods for nuclear engineering with emphasis on thermal-hydraulics, Monte Carlo methods, multiphysics, high performance computing, and open source software development. April is the PI for Cardinal, an open-source high-fidelity multiphysics application which is a winner of the 2023 R&D 100 Award. Prior to joining UIUC, she was a Fellow in the Computational Sciences Division at Argonne, where she led and contributed to many modeling and simulation efforts for advanced reactors. She is also an expert on pebble bed reactor thermal-hydraulics, and was the original developer of the Pronghorn porous media MOOSE-based application. She has a PhD in Nuclear Engineering from the University of California, Berkeley (2020).
Xu Wu
Xu is an Assistant Professor of Nuclear Engineering at North Carolina State University. His main research interests include: uncertain quantification, Bayesian inverse problems, model discrepancy analysis, scientific machine learning and deep generative modeling. Xu received his BS in Nuclear Engineering from Shanghai Jiao Tong University in 2011 and PhD in Nuclear Engineering from University of Illinois at Urbana - Champaign in 2017. Prior to joining NC State in 2019, he worked as a Postdoctoral Research Associate at the Department of Nuclear Science and Engineering at MIT.
Kevin Zwijsen
Kevin is a research consultant at the Nuclear Research and Consultancy Group (NRG) in The Netherlands. He obtained his BSc and MSc in Mechanical Engineering from the Eindhoven University of Technology, specializing in fundamental and Computational Fluid Dynamics (CFD) and heat transfer. He then worked on a PhD at McGill University in Montréal, Canada, in the department of Atmospheric and Oceanic Sciences, studying the “Effects of Turbulence on Droplet Growth in Clouds”. He has been in his present position since 2016, being part of the Reactor Analysis & operational Support (RAS) team at NRG. His research interests are Fluid-Structure Interaction (FSI), being the interaction between the coolant and structural components of a nuclear power plant, Multi-Scale Simulations, which involves the coupling of CFD and System Thermal Hydraulics (STH) codes, and Reactor Pool Modeling of Fast Reactors, studying the thermal hydraulic behavior of the coolant in the full primary system of the reactor.