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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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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Fusion Science and Technology
Latest News
ARPA-E announces $40 million to develop transmutation technologies for UNF
The Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E) announced $40 million in funding to develop cutting-edge technologies to enable the transmutation of used nuclear fuel into less-radioactive substances. According to ARPA-E, the new initiative addresses one of the agency’s core goals as outlined by Congress: to provide transformative solutions to improve the management, cleanup, and disposal of radioactive waste and spent nuclear fuel.
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.