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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
2023 ANS Winter Conference and Expo
November 12–15, 2023
Washington, D.C.|Washington Hilton
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Nuclear Science and Engineering
Fusion Science and Technology
National Museum of Nuclear Science and History explores “atomic” culture
For many of us, the toys of our childhood leave indelible marks on our consciousness, affecting our long-term perceptions and attitudes about certain things. Hot Wheels may inspire a lifelong fascination with fast, flashy automobiles, while Barbies might shape ideas about beauty and self-image. For the generation who grew up during the Atomic Age—the post–World War II era from roughly the mid-1940s to the early 1960s—the toys, games, and entertainment of their childhoods might have included things like atomic pistols, atomic trains, rings with tiny amounts of radioactive elements, and comic books, puzzles, and music about nuclear weapons.
Monday, October 4, 2021|5:30–7:00PM EDT
Katherine Royston (ORNL)
Todd J. Urbatsch (LANL)
Joe Coale (NC State Univ.)
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Consistent Temperature and Intensity Calculations From Deterministic Phonon Transport
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.)
A Hybrid Deterministic-Stochastic Method for the Calculation of Dose Rate in Reactor Dismantling Operations
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
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
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
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
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
Alisha Kasam-Griffith (ANL), Adam Nelson (ANL), Florent Heidet (ANL)
Validation of RAPID's Algorithm for Control Rods Movement Using the JSI TRIGA Reactor
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
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
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
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
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
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
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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