ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
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
Mar 2025
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Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
El Salvador: Looking to nuclear
In 2022, El Salvador’s leadership decided to expand its modest, mostly hydro- and geothermal-based electricity system, which is supported by expensive imported natural gas and diesel generation. They chose to use advanced nuclear reactors, preferably fueled by thorium-based fuels, to power their civilian efforts. The choice of thorium was made to inform the world that the reactor program was for civilian purposes only, and so they chose a fuel that was plentiful, easy to source and work with, and not a proliferation risk.
Suk-Kwon Kim, Eo Hwak Lee, Jae-Sung Yoon, Dong Won Lee, Duck-Hoi Kim, Seungyon Cho
Fusion Science and Technology | Volume 64 | Number 2 | August 2013 | Pages 288-292
Divertor and High-Heat-Flux Components | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 1), Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST13-A18091
Articles are hosted by Taylor and Francis Online.
Korean high heat flux test facility for the plasma facing components of nuclear fusion machines will be constructed to evaluate the performance of each component. This facility for plasma facing materials will be equipped with an electron beam gun with a 60 kV acceleration voltage. The system also includes a 300 kW power supply system, a vacuum test chamber, and a beryllium filtration system for the ITER first wall mockups. First, a commissioning test has been scheduled to establish the installation and preliminary performance experiments of the copper hypervapotron mockups and evaluate the thermo-hydraulic specifications. Second, a qualification test will be performed to evaluate the CuCrZr duct liner in the ITER neutral beam injection facility and the ITER first wall small-scale mockups of the semi-prototype, at up to 1.5 and 5 MW/m2 high heat flux, respectively. This electron beam system will be used to qualify the specifications of the plasma facing components in the KSTAR tokamak and other fusion devices.