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.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
Dec 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
January 2026
Nuclear Technology
December 2025
Fusion Science and Technology
November 2025
Latest News
Blades-in turbine inspections at Quad Cities set new benchmark for Constellation
When Constellation decided to install replacement Alstom low-pressure turbines at three of its boiling water reactor plants more than 15 years ago, one benefit was knowing the new turbines should operate reliably—and without major inspections—for several years.
Advances in Thermal Hydraulics (ATH 2022)
Technical Session
Tuesday, June 14, 2022|1:00–2:45PM PDT|Redondo
Session Chair:
Subash Sharma (UMass Lowell)
Alternate Chair:
Trevor Howard (Oregon State)
Session Organizers:
Matthew D. Zimmer (Naval Nuclear Lab)
Xu Wu (NCSU)
To access paper attachments, you must be logged in and registered for the meeting.
Register NowLog In
CFD Analysis of the Sodium-Water Reaction in the Minichannel of PCSG Designed for SFR
Taewoo Kim (Korea Univ. Science and Technology), Hyun-Sik Park (KAERI), Sang Ji Kim (KAERI)
Paper
A Multiphysics Framework Using High Resolution DNS to Optimize Conditions for Plasma Formation
Naveen Pillai (NCSU), Nicholas L. Sponsel (NCSU), Katharina Stapelmann (NCSU), Igor A. Bolotnov (NCSU)
A Conceptual Study of Air Curtain on the Reactor Vessel Auxiliary Cooling System
Jaejin Choi (KAIST), Yong Hoon Jeong (KAIST)
Development of Integrated Safety Analysis Code with Capability of Detailed Simulation for Multiple Fuel Rods
Yunseok Lee (Incheon National Univ.), Jaeseung Suh (SenTech Co.), Taewan Kim (Incheon National Univ.)
LES of Natural Convection Along the Vertical Wall Applied for the Scale of Small Modular Reactor ( Ra*≈10^19)
Songzhi Yang (CEA), Ulrich Bieder (CEA)
To join the conversation, you must be logged in and registered for the meeting.