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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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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Fusion Science and Technology
Latest News
X-energy receives federal tax credit for TRISO fuel facility
Advanced reactor company X-energy has been awarded $148.5 million in tax credits under the Inflation Reduction Act for construction of its TRISO-X fuel fabrication facility in Oak Ridge, Tenn.
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.