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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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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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.
Viorel Fugaru, George Bubueanu, Catalin Stelian Tuta, Mihail-Razvan Ioan
Fusion Science and Technology | Volume 76 | Number 3 | April 2020 | Pages 347-350
Technical Paper | doi.org/10.1080/15361055.2020.1712008
Articles are hosted by Taylor and Francis Online.
The Tritium Laboratory at Horia Hulubei National Institute for Physics and Nuclear Engineering was initially licensed in 1976 and completely refurbished in 2011 as a unique isotope laboratory focused on tritium handling and processing to conduct a variety of scientific experiments. During laboratory renovation, different types of solid radioactive waste or potential waste contaminated with tritium were created: bricks, mortars, cements, false ceiling (polyvinyl chloride), linoleum, rubber, etc.
In order to fulfill all the requirements of the license issued by the Romanian regulatory body, the characterization of the physical, chemical, and radiological properties of the waste, in order to establish the need for further treatment, conditioning, and for storage or disposal, was mandatory. The present work treats the development of a method for the determination of tritium activity in the solid waste according to the operation licensing framework. The measurement results, regarding the tritium-specific activity in different solid waste resulting from the renovation of the laboratory, are presented in this paper.