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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
2022 ANS Annual Meeting
June 12–16, 2022
Anaheim, CA|Anaheim Hilton
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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June 2022
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Latest News
Deadline extended to apply for ANS's 2023 ANS Congressional Fellowship
The deadline for applications to the ANS's Glenn T. Seaborg Congressional Science and Engineering Fellowship has been extended. All ANS members are invited to apply to help the Society fulfill its strategic goal of informing nuclear public policy.
All applications and supporting documents are now due by 11:59 p.m. (EDT) on Monday, May 23.
Technical Session|Sponsored by RPD
Monday, June 14, 2021|2:15–4:00PM (3:15–5:00PM EDT)
Session Chair:
Pavel V. Tsvetkov (TAMU)
Session Organizer:
Alternate Chair:
Massimiliano Fratoni
Staff Producer:
Ashley Jiminian (ANS)
This is a standing RPD session with papers on all reactor analysis topics of contemporary interest.
To access the session recording, you must be logged in and registered for the meeting.
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To access paper attachments, you must be logged in and registered for the meeting.
Multiphysics Benchmark Results from Moltres
Sun Myung Park (Univ. of Illinois Urbana-Champaign), Kathryn D. Huff (Univ. of Illinois Urbana-Champaign)
Summary
Cerberus: A MOOSE-Based Application for Solving the SP3 Equations
Roberto E. Fairhurst Agosta (Univ. of Illinois at Urbana-Champaign), Kathryn D. Huff (Univ. of Illinois Urbana Champaign)
Verification of the Multi-Group Generation Capability of FRENDY Nuclear Data Processing Code for Recent Nuclear Data through Comparison of One-group Reaction Rates
Akio Yamamoto (Nagoya Univ.), Kenichi Tada (Japan Atomic Energy Agency), Go Chiba (Hokkaido Univ.), Tomohiro Endo (Nagoya Univ.)
Large-Scale Whole-Core Monte Carlo Cycle Depletion Employing GPUs
Kyung Min Kim (Seoul Nat'l Univ.), Namjae Choi (Seoul Nat'l Univ.), Han Gyu Lee (Seoul Nat'l Univ.), Han Gyu Joo (Seoul Nat'l Univ.)
Presentation Video
Validation of SCALE 6.2.4 and ENDF/B-VII.1 Data Libraries for Nuclide Inventory Analysis in PWR Used Fuel
Germina Ilas (ORNL), Briana Hiscox (ORNL)
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