ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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
May 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Deep Isolation validates its disposal canister for TRISO spent fuel
Nuclear waste disposal technology company Deep Isolation announced it has successfully completed Project PUCK, a government-funded initiative to demonstrate the feasibility and potential commercial readiness of its Universal Canister System (UCS) to manage TRISO spent nuclear fuel.
Technical Session|Sponsored by THD
Tuesday, November 15, 2022|1:00–2:45PM MST|Sonoran 3
Session Chair:
Igor Bolotnov (NCSU)
Alternate Chair:
Kaeley Stevens
Session Organizer:
Guanyi Wang (ANL)
To access paper attachments, you must be logged in and registered for the meeting.
Register NowLog In
HI-STORM Overpack and MPC-32 Thermal-Hydraulic Model with MOOSE Framework
1:00–1:20PM MST
Sinan Okyay (Penn State), Elia Merzari (Penn State), Fande Kong (INL), David Reger (Penn State), Peter German (INL), Victor Coppo Leite (Penn State), Guillaume Giudicelli (INL), Alexander D. Lindsay (INL)
Paper
Structural Response of University of Missouri Research Reactor Low-Enriched Uranium Fuel Elements Under Hydraulic and Thermal Load
1:20–1:40PM MST
Guanyi Wang (ANL), Cezary Bojanowski (ANL), Dhongik Yoon (ANL), John Stillman (ANL), David Jaluvka (ANL), Leslie Foyto (Univ. Missouri-Columbia Research Reactor), Erik Wilson (ANL)
A Three-Dimensional Cartesian Thermal-Hydraulic Solver in the Residual Formulation of CTF
1:40–2:00PM MST
Lance Bullerwell (NCSU), Agustin Abarca (NCSU), Maria Avramova (NCSU), Jason Hou (NCSU)
MELCOR Model Development of the General Atomics Fast Modular Reactor: Transient Accident Analysis
2:00–2:20PM MST
WooHyun Jung (Univ. Wisconsin, Madison), Cole Dunbar (Univ. Wisconsin, Madison), Jun Wang (Univ. Wisconsin, Madison), Michael Corradini (Univ. Wisconsin, Madison)
An Equation-Free Based Coupling Approach for Multiscale Fluid Dynamics and Heat Transfer Analysis
2:20–2:40PM MST
Qiyun Cheng (Rensselaer Polytechnic Institute), Huihua Yang (Rensselaer Polytechnic Institute), Shanbin Shi (Rensselaer Polytechnic Institute), Wei Ji (Rensselaer Polytechnic Institute)
To join the conversation, you must be logged in and registered for the meeting.
