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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Latest News
DOE issues RFQ for clean-energy projects at WIPP
The Department of Energy has issued a request for qualifications (RFQ) for interested parties that are looking to establish carbon pollution–free electricity (CFE) projects at its Waste Isolation Pilot Plant site in New Mexico.
Takumi Hayashi, Masayuki Yamada, Takumi Suzuki, Yuji Matsuda, Kenji Okuno
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1503-1508
Tritium Waste Management and Discharge Control | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30625
Articles are hosted by Taylor and Francis Online.
A new tritium removal system using gas separation membranes has been studied to develop more compact and cost-effective system for a fusion reactor. To obtain necessary parameters, which are directly scale able to the ITER Atmospheric Detritiation System, the basic tritium recovery performance was investigated with a scaled polyimide membrane module (hollow-filament type : 10 m3/hr ) loop. The result shows that the H2 recovery ratio from N2 or Air was more than 99 % or about 97 %, respectively, at flow rate ratio of permeated/feed =0.1, feed & permeated side pressures = 2580 & 80 torr, and module temp. = 293 K. Tritium (HT) recovery function was almost the same of H2 recovery, even though the total hydrogen concentration was a few ppm in the feed of module. H2O recovery performance was better than hydrogen recovery. These recovery functions were improved effectively decreasing the pressure ratio of permeated/feed of module.
