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
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC 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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Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Siting of Canadian repository gets support of tribal nation
Canada’s Nuclear Waste Management Organization (NWMO) announced that Wabigoon Lake Ojibway Nation has indicated its willingness to support moving forward to the next phase of the site selection process to host a deep geological repository for Canada’s spent nuclear fuel.
C. Muirhead, H. Li, K. Pilatzke, M. Byers, R. Carson, H. Boniface, S. Suppiah
Fusion Science and Technology | Volume 71 | Number 3 | April 2017 | Pages 281-285
Technical Paper | doi.org/10.1080/15361055.2017.1290974
Articles are hosted by Taylor and Francis Online.
Canadian Nuclear Laboratories (CNL) is developing a Proton Exchange Membrane-based (PEM) electrolyser intended for tritium removal. Commercially available Nafion® N-1110 membranes have been exposed to tritiated water (with a β activity of about 37 GBq/mL) prepared in the Tritium Facility at CNL. Three equivalent batches of Nafion® N-1110 membranes (each with a dimension of 4 cm × 4 cm) were exposed to β-doses of 67 kGy, 155 kGy, and 255 kGy, respectively.
The exposed membranes required decontamination for characterization and testing. A few different decontamination methods have been experimentally studied. These methods can be categorized as water elution and chemical soaking. The measured tritium concentration in eluent decreased quickly in the first 30 days of water elution, followed by a slow decay afterwards until reaching a plateau after about 100 days. Chemical soaking proved to be more effective than the water elution method and high temperature facilitated the tritium release.