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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.
2021 ANS Winter Meeting and Technology Expo
November 30–December 3, 2021
Washington, DC|Washington Hilton
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Results of advanced nuclear survey released
The U.S. Nuclear Industry Council has released the results of its 2021 Advanced Nuclear Survey.
The results, issued late last month, include information from 17 USNIC-member advanced nuclear developers on topics such as federal and state policies, types of reactors in development, U.S./Canadian licensing, need for control room operators, Nuclear Regulatory Commission fees, Department of Energy programs, and high-assay low-enriched uranium (HALEU). In addition, 24 companies (the 17 member firms plus seven nonmember firms) provided their perspectives on the NRC’s planned 10 CFR Part 53 regulation of advanced reactors.
Monday, October 4, 2021|4:30–6:00PM (5:30–7:00PM EDT)|Salon A
Todd J. Urbatsch (LANL)
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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)
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)
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)
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