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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
August 2024
Nuclear Technology
July 2024
Fusion Science and Technology
Latest News
NRC engineers share their expertise at the University of Puerto Rico
Robert Roche-Rivera and Marcos Rolón-Acevedo are licensed professional engineers who work at the U.S. Nuclear Regulatory Commission. They are also alumni of the University of Puerto Rico–Mayagüez (UPRM) and have been sharing their knowledge and experience with students at their alma mater since last year, serving as adjunct professors in the university’s Department of Mechanical Engineering. During the 2023–2024 school year, they each taught two courses: Fundamentals of Nuclear Science and Engineering, and Nuclear Power Plant Engineering.
George Ana, Anisia Bornea, Ciprian Bucur, Alina Niculescu, Felicia Vasut, Ovidiu Balteanu, Marius Zamfirache
Fusion Science and Technology | Volume 76 | Number 3 | April 2020 | Pages 321-326
Technical Paper | doi.org/10.1080/15361055.2020.1711854
Articles are hosted by Taylor and Francis Online.
Whether they are based on fusion (JET, ITER, DEMO) or fission (e.g., CANDU type) or are cooled using molted salts [molten salt reactors (MSRs)], nuclear reactors generate significant amounts of waste in the form of low-level tritiated light water or heavy water, which generates risks for the environment and radiological risks for operating personnel. Given the wide range of tritium concentrations of tritiated water waste, processing it efficiently is possible only if the process is based on the combined process of liquid phase catalitic exchange and electrolysis of water. During this process, tritium is concentrated as tritiated water, which reduces the amount of waste and concentrates the water at the isotopic level high enough for further processing in view of tritium recovery, employing isotopic transfer in gas form. This paper reports on the modification of an industrial hydrogen generator in view of tritium compatibility to be used for further processing of tritiated (heavy) water for tritium recovery. Additionally, analysis will be made, and results will be presented on what will be the tritium/deuterium concentration profile in the generator and what influence the water holdup will have on the isotope concentration.