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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
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Advanced Reactor Safety (ARS)
Technical Session
Tuesday, June 18, 2024|10:00–11:45AM PDT|Palm A
Session Chair:
Dennis W. Henneke
Session Organizer:
Alternate Chair:
Aslak Stubsgaard
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The Co-Evolution of the GE-Hitachi BWRX-300 Probabilistic Safety Assessment and Plant Design
10:00–10:20AM PDT
Nathan DeKett (GE - Hitachi Nuclear Energy), Dennis Henneke (GE-Hitachi Nuclear Energy)
Paper
Application of the GIF Safety Design Criteria and Safety Design Guidelines on Decay Heat Removal System to Next Generation Sodium-Cooled Fast Reactor in Japan
10:20–10:40AM PDT
Hidemasa Yamano (Japan Atomic Energy Agency), Satoshi Futagami (Japan Atomic Energy Agency), Koichi Higurashi (Mitsubishi FBR Systems, Inc.)
Application of the RMPS+ Method to the BWRX-300 Isolation Condenser System: An Introduction
10:40–11:00AM PDT
Tyra Gordon (GE Hitachi Nuclear Energy), Nathan DeKett (GE Hitachi Nuclear Energy), Dennis Henneke (GE Hitachi Nuclear Energy), Jonathan Li (GE Hitachi Nuclear Energy)
Development and Demonstration of a Prototype Molten Salt Sampling System
11:00–11:20AM PDT
Megan Harkema (Vanderbilt Univ.), Steven Krahn (Vanderbilt Univ.), Paul Marotta (Vanderbilt Univ.), Adam Burak (Univ. Michigan), Xiaodong Sun (Univ. Michigan), Piyush Sabharwall (INL)
Application of the GIF Safety Design Criteria and Safety Design Guidelines on Reactor Shutdown System to Next Generation Sodium-Cooled Fast Reactor in Japan
11:20–11:40AM PDT
Hidemasa Yamano (Japan Atomic Energy Agency), Satoshi Futagami (Japan Atomic Energy Agency), Akihiro Shibata (Mitsubishi FBR Systems, Inc.)
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