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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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!
Latest Magazine Issues
Jun 2025
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Nuclear Science and Engineering
July 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Technical Session
Monday, October 4, 2021|5:30–7:00PM EDT
Session Chair:
Katherine Royston (ORNL)
Session Organizer:
Todd J. Urbatsch (LANL)
Student Producer:
Joe Coale (NC State Univ.)
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Consistent Temperature and Intensity Calculations From Deterministic Phonon Transport
5:30–5:35PM EDT
Nicholas H. Whitman (Oregon State Univ.), Todd S. Palmer (Oregon State Univ.), P. Alex Greaney (Univ. of California - Riverside), Dmitriy Y. Anistratov (NC State Univ.)
Paper
Reference
A Hybrid Deterministic-Stochastic Method for the Calculation of Dose Rate in Reactor Dismantling Operations
5:35–5:40PM EDT
Ettore Guadagni (CEA), Yannick Pénéliau (CEA), Jean Michel Létang (Univ. de Lyon), François-Xavier Hugot (CEA), Cindy Le Loirec (CEA)
Reference — Poster
Radiation Shielding Calculations at VTT Centre for Nuclear Safety Using the Serpent 2 Monte Carlo Code
5:40–5:45PM EDT
Jaakko Leppänen (VTT Technical Research Centre of Finland), Mika Jokipii (VTT Technical Research Centre of Finland)
Neutronics Simulation of the Molten Salt Reactor Experiment With SCALE/Shift and Serpent/PARCS
5:45–5:50PM EDT
Jin Li (Univ. of Michigan), Shai Kinast (Univ. of Michigan), Volkan Seker (Univ. of Michigan), Jipu Wang (Univ. of Michigan), Andrew Ward (Univ. of Michigan), Brendan Kochunas (Univ. of Michigan), Thomas Downar (Univ. of Michigan), Ugur Mertyurek (ORNL)
A Novel Monte Carlo Leakage Correction for Serpent 2
5:50–5:55PM EDT
Ville Valtavirta (VTT Technical Research Centre of Finland), Jaakko Leppänen (VTT Technical Research Centre of Finland)
Direct Calculation of Safety-Related Parameters for Coupled Transients Using Monte Carlo Neutronics Plus Subchannel Thermal-Hydraulics
5:55–6:00PM EDT
Diego Ferraro (Karlsruhe Institute for Technology), Manuel García (Karlsruhe Institute for Technology), Ville Valtavirta (VTT Technical Research Centre of Finland), Uwe Imke (Karlsruhe Institute for Technology), Riku Tuominen (VTT Technical Research Centre of Finland), Jaakko Leppänen (VTT Technical Research Centre of Finland Ltd), Victor Sanchez-Espinoza (Karlsruhe Institute for Technology)
Multigroup Cross-Section Generation for Versatile Test Reactor Experiments Analysis
6:00–6:05PM EDT
Alisha Kasam-Griffith (ANL), Adam Nelson (ANL), Florent Heidet (ANL)
Validation of RAPID's Algorithm for Control Rods Movement Using the JSI TRIGA Reactor
6:05–6:10PM EDT
Valerio Mascolino (Virginia Tech), Alireza Haghighat (Virginia Tech), Anže Pungerčič (Jožef Stefan Institute), Luka Snoj (Jozef Stefan Institute)
Reference — Poster PDF
Modelling of the OPEN100 Reactor with the Serpent-2 Code
6:10–6:15PM EDT
Anže Mihelčič (Jozef Stefan Institute), Anze Pungercic (Jozef Stefan Institute), Dusan Calic (Jozef Stefan Institute), Luka Snoj (Jozef Stefan Institute)
Improvements on Power Calibration and Core Monitoring at the Penn State Breazeale Reactor With MCNP
6:15–6:20PM EDT
Gokhan Corak (Penn State Univ.), William J. Walters (Penn State Univ.)
An Adaptation of the Coarse Mesh Transport (COMET) Method for Improved Parallelism Targeting GPU Architectures
6:20–6:25PM EDT
Paul Burke (Georgia Institute of Technology), Farzad Rahnema (Georgia Institute of Technology), Dingkang Zhang (Georgia Institute of Technology)
Monte Carlo Scalability on Extreme Memory Computing Nodes
6:25–6:30PM EDT
David P. Griesheimer (Naval Nuclear Laboratory), Peter S. Dobreff (Naval Nuclear Laboratory), Roberto Gomez (Pittsburgh Supercomputing Center)
New Route in TRIPOLI-4® for Radiation Dosimetry Calculations Using ICRP 110 Voxel Phantoms
6:30–6:35PM EDT
Yi-Kang Lee (CEA), François-Xavier Hugot (CEA), Yue Jin (CEA)
3-D Monte Carlo vs SN Deterministic Radiation Transport Methods Supporting an Optimized Neutron Imaging Source at the Utah TRIGA Reactor
6:35–6:40PM EDT
Michael J. Hartos (Univ. of Utah), Meng-Jen Wang (Univ. of Utah), Glenn E. Sjoden (Univ. of Utah)
Attachment — Poster for M&C Session
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