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Division Spotlight
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.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Feb 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
March 2025
Nuclear Technology
February 2025
Fusion Science and Technology
Latest News
Arizona utilities trio looks to add nuclear power
The top three utilities in Arizona are teaming up to explore opportunities to add nuclear generation facilities in the state.
Arizona Public Service (APS), Salt River Project (SRP), and Tucson Electric Power (TEP) announced in a February 5 news release that they are working together to assess possible sites, including retiring coal plants. The group is looking at possibilities for both small modular reactors—units generating 300 MW or less—and potential large reactor projects, which could generate nearly five times the power.
Technical Session
Wednesday, October 6, 2021|10:40AM–12:20PM EDT
Session Chair:
Brendan Kochunas (Univ. of Michigan)
Session Organizers:
Benoit Forget (MIT)
William Wieselquist (ORNL)
Student Producer:
K. Lisa Reed (Georgia Tech)
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Preliminary Implementation and Application of an Electrical Equivalent Circuit for Neutron Diffusion Modeling
10:40–11:05AM EDT
Naiki Kaffezakis (Georgia Institute of Technology), Dan Kotlyar (Georgia Institute of Technology)
Paper
Preliminary Investigation of Arbitrary CAD Geometry and Unstructured Mesh With 2D Method of Characteristics in MPACT
11:05–11:30AM EDT
Kyle Vaughn (Univ. of Michigan), Brendan Kochunas (Univ. of Michigan)
Development of Estimation Method for Prompt Neutron Decay Constant Using Dynamic Mode Decomposition
11:30–11:55AM EDT
Fuga Nishioka (Nagoya Univ.), Yuhei Fukui (Nagoya Univ.), Tomohiro Endo (Nagoya Univ.), Akio Yamamoto (Nagoya Univ.), Masao Yamanaka (Kyoto Univ.), Cheol Ho Pyeon (Kyoto Univ.)
A Transport Corrected SP3 Solver Development with Nodal Expansion Method
11:55AM–12:20PM EDT
Yuchao Xu (NC State Univ.), Jason Hou (NC State Univ.), Kostadin Ivanov (NC State Univ.)
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