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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
May 2025
Fusion Science and Technology
Latest News
The 2025 ANS election results are in!
Spring marks the passing of the torch for American Nuclear Society leadership. During this election cycle, ANS members voted for the newest vice president/president-elect, treasurer, and six board of director positions (four U.S., one non-U.S., one student). New professional division leadership was also decided on in this election, which opened February 25 and closed April 15. About 21 percent of eligible members of the Society voted—a similar turnout to last year.
Technical Session|Reactor Design and Analysis
Tuesday, April 23, 2024|10:15AM–12:00PM PDT|Franciscan A
Session Chair:
Emily R. Shemon
Alternate Chair:
Nicolas E. Stauff
Session Organizer:
Eva E. Davidson
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Coupled Simulation of the Sodium Cooled Fast Reactor BN-800 with the GRS System ATHLET-PARCS
10:15–10:35AM PDT
J. Bousquet (GRS), Y. Perin (GRS), R. Henry (GRS)
Paper
Breakeven Feasibility Study of Chlorine-Based MSFR with Discontinuous and Continuous Fuel Processes
10:35–10:55AM PDT
Eunhyug Lee (KAIST), Taesuk Oh (KAIST), Yonghee Kim (KAIST)
New Design Core Options of Micro-Modular Lead Cooled Fast Reactors (MMLFR) for Facilitating Natural Circulation
10:55–11:15AM PDT
Seungnam Lee (Hanyang Univ.), Ser Gi Hong (Hanyang Univ.)
Neutronic Benchmark on the Westinghouse Lead Fast Reactor
11:15–11:35AM PDT
Nicolas E. Stauff (ANL), Ahmed Abdelhameed (ANL), Alex Levinsky (Westinghouse Electric Co.), Fausto Franceschini (Westinghouse Electric Co.)
Neutronic Analysis of MOX-1000MWth Fast Reactor by Two-Step System Code MCS/RAST-F
11:35–11:55AM PDT
Saisundar Mohanty (Ulsan Nat'l Institute Science and Technology), Tran Quoc Tuan (Ulsan Nat'l Institute Science and Technology), Fathurrahman Setiawan (Ulsan Nat'l Institute Science and Technology), Murat Serdar Aygul (Ulsan Nat'l Institute Science and Technology), DeokJung Lee (Ulsan Nat'l Institute Science and Technology)
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