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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
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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Nuclear Science and Engineering
February 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Fermilab center renamed after late particle physicist Helen Edwards
Fermi National Accelerator Laboratory’s Integrated Engineering Research Center, which officially opened in January 2024, is now known as the Helen Edwards Engineering Center. The name was changed to honor the late particle physicist who led the design, construction, commissioning, and operation of the lab’s Tevatron accelerator and was part of the Water Resources Development Act signed by President Biden in December 2024, according to a Fermilab press release.
H. J. Ahn, J. Park, K. Song, B-C Na, S. Rosanvallon, D. Stout
Fusion Science and Technology | Volume 60 | Number 3 | October 2011 | Pages 1006-1009
Measurement, Monitoring, and Accountancy | Proceedings of the Ninth International Conference on Tritium Science and Technology | doi.org/10.13182/FST11-A12586
Articles are hosted by Taylor and Francis Online.
ITER is trying to develop destructive and non-destructive methods of tritium measurement for discarded radwaste components. The ITER Type B(medium activity with long life) metallic radwastes that need tritium measurement are mainly Divertor Cassette Body, Blanket Modules, Test Blanket Module Port Plug, Torus Cryopump, etc. It has been known that 107 Bq/g of tritium is distributed within 1 mm depth from the surface of the metallic radwastes. The metallic radwastes generated from maintenance period of ITER facility will be transferred to the Hot Cell Facility (HCF) for treatment including cutting, tritium removal and pre-packaging, followed by being shipped to the disposal facility after interim storage at ITER site.In this study, the radiochemical analysis methods of tritium measurement for ITER type B metallic radwastes were reviewed. Especially, two experimental methods, chemical acid leaching method (CALM) and heating method (HM,) were compared with each others to suggest the most suitable method for tritium measurement. The recovery yield of tritium standards for CALM and HM showed excellent results of 98 and 90 %, respectively. Since HM requires post treatment of extracted tritium species due to impurities, as shown in the analysis of sample from Nuclear Power Plant, CALM was considered more efficient method than HM for tritium analysis of Type B metallic radwastes.