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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
R. Carrera, W. D. Booth, J. L. Anderson, T. Bauer, D. Coffin, T. A. Parish†
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1629-1633
Material and Tritium | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29574
Articles are hosted by Taylor and Francis Online.
This paper outlines the preliminary conceptual design of a minimum—cost tritium system for a basic ignition experiment whose objective is to produce and control fusion ignited plasmas for scientific study. A system without tritium recycling and tritium reprocessing is envisioned. The fueling requirements can be satisfied by using a tritium storage tank with 20 kCi absorbed in a uranium bed which will be delivered to the facility every month (about 100 ignition pulses). Fueling needs will be supplied by thermal heating of the uranium bed and subsequent gas puffing of the tritium into the tokamak vacuum vessel. A modular vacuum pumping system is considered (6 × 880 ℓ/sec). Tritiated liquid effluents are eliminated by using oilless—bearing pumps. A thin carbon film is applied by glow discharge over the first wall to contain the tritium in the plasma chamber (by saturating the C film). The overall cost of the tritium system is estimated to be less than $3 million.