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
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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!
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Nuclear Science and Engineering
January 2025
Nuclear Technology
Fusion Science and Technology
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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Technical Session|Sponsored by RPD
Thursday, June 11, 2020|10:00–11:45AM EDT
Session Chair:
Jason Hearne (LANL)
Alternate Chair:
Pavel Tsvetkov (LANL)
Session Organizer:
Track Organizer:
Staff Producer:
Jessica Vazquez (American Nuclear Society)
To access the session recording, you must be logged in and registered for the meeting.
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A Unified Form of Stabilized Finite Element Methods for Solving the First-order Neutron Transport Equation
Liangzhi Cao (Xi’an Jiaotong Univ.), Chao Fang (Xi’an Jiaotong Univ.), Hongchun Wu (Xi’an Jiaotong Univ.)
Paper
Relaxation of Quasi-Static Approach via Polynomial Interpolation in the Predictor Corrector Quasi-Static Method
T. Oh (KAIST), Yonghee Kim (KAIST)
Unstructured Mesh-Grid Multi-Physics Analysis with Monte Carlo iMC Code for Advanced Fuel Elements
Hyeontae Kim (KAIST), Yonghee Kim (KAIST)
Conceptual Safety Design Report for the Versatile Test Reactor
Doug Gerstner (INL), Jason Andrus (INL), Troy Reiss (INL)
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