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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
Nuclear and Emerging Technologies for Space (NETS 2023)
May 7–11, 2023
Idaho Falls, ID|Snake River Event Center
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
Mar 2023
Jan 2023
Latest Journal Issues
Nuclear Science and Engineering
April 2023
Nuclear Technology
Fusion Science and Technology
February 2023
Latest News
IAEA launches comic book contest for teens
The International Atomic Energy Agency is inviting teens aged 14 to 18 to submit original comic book pages depicting a space-based nuclear science experiment on agricultural seeds that the agency is conducting with the United Nations’ Food and Agricultural Organization (FAO). The contest is offering prizes, including publication of the winning designs on the IAEA website, for the champion and finalists. The deadline for April 16.
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)
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HI-STORM Overpack and MPC-32 Thermal-Hydraulic Model with MOOSE Framework
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)
Summary
Structural Response of University of Missouri Research Reactor Low-Enriched Uranium Fuel Elements Under Hydraulic and Thermal Load
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
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
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
Qiyun Cheng (Rensselaer Polytechnic Institute), Huihua Yang (Rensselaer Polytechnic Institute), Shanbin Shi (Rensselaer Polytechnic Institute), Wei Ji (Rensselaer Polytechnic Institute)
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