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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.
Materials in Nuclear Energy Systems (MiNES 2023)
December 10–14, 2023
New Orleans, LA|New Orleans Marriott
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
Framatome and USNC team up to produce TRISO fuel at Framatome facility
Framatome Inc. and Ultra Safe Nuclear Corp. (USNC) signed an agreement on November 28 at the World Nuclear Exhibition in Paris, France, establishing a joint venture to manufacture nuclear fuel for USNC’s gas-cooled microreactor and other advanced reactor designs. Working together, the companies plan to produce commercial quantities of TRISO fuel particles and USNC’s proprietary Fully Ceramic Microencapsulated (FCM) fuel, which contains TRISO fuel particles within a ceramic fuel pellet.
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.
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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.)
Presentation Video (Visible to Attendees)
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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