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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
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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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.
Masabumi Nishikawa
Fusion Science and Technology | Volume 22 | Number 1 | August 1992 | Pages 135-137
Technical Paper | D-3He/Fusion Reactor | doi.org/10.13182/FST92-A30063
Articles are hosted by Taylor and Francis Online.
Problems related to tritium in the fuel cycle of a D-3He fusion reactor are discussed. About 15 g/day of tritium is estimated to be exhausted from a 1-GW(electric) D-3He reactor. The cumulative amount of tritium in storage reaches ∼80 kg after 30 yr of operation if all the tritium exhausted from the plasma is confined.