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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
2023 ANS Annual Meeting
June 11–14, 2023
Indianapolis, IN|Marriott Indianapolis Downtown
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
Fusion Science and Technology
Route readiness elements in a large-scale spent nuclear fuel transportation system
The scale and duration of a national campaign to transport spent nuclear fuel (SNF) from commercial nuclear power plants around the United States would be unprecedented. A meticulous level of planning that considers many elements is needed to inspire public confidence and support.
Technical Session|Sponsored by RPD
Monday, June 14, 2021|3:15–5:00PM EDT
Pavel V. Tsvetkov (TAMU)
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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Multiphysics Benchmark Results from Moltres
Sun Myung Park (Univ. of Illinois Urbana-Champaign), Kathryn D. Huff (Univ. of Illinois Urbana-Champaign)
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.)
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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