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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Nuclear Technology
Fusion Science and Technology
July 2025
Latest News
Hash Hashemian: Visionary leadership
As Dr. Hashem M. “Hash” Hashemian prepares to step into his term as President of the American Nuclear Society, he is clear that he wants to make the most of this unique moment.
A groundswell in public approval of nuclear is finding a home in growing governmental support that is backed by a tailwind of technological innovation. “Now is a good time to be in nuclear,” Hashemian said, as he explained the criticality of this moment and what he hoped to accomplish as president.
S. D. Bondarenko, I. A. Alekseev, O. A. Fedorchenko, K. A. Konoplev, Т. V. Vasyanina
Fusion Science and Technology | Volume 71 | Number 4 | May 2017 | Pages 605-609
Technical Note | doi.org/10.1080/15361055.2017.1290484
Articles are hosted by Taylor and Francis Online.
Heavy water is used as a neutron moderator and coolant in nuclear power and research reactors. During operation of heavy water reactors, heavy water becomes contaminated with tritium and protium. Protium comes from various sources, such as a result of isotope exchange from constructional materials and sorbents, from the atmosphere as water vapor, and from the faulty equipment in the form of water. Tritium is produced in heavy water owing to neutron capture by deuterium atoms. Thus, heavy water reactors require facilities to keep deuterium concentrations within operating margins and remove tritium. A schematic diagram of a detritiation plant has been developed to maintain the characteristics of heavy water in the reflector of reactor. The plant is designed to address the problems related to management of heavy water at the reactor site. Protium recovery capacity of the plant is not a fixed value. It can vary widely depending on the actual leakage of light water in a heavy water reactor loop. The initial data for modeling were obtained in the course of long-term operation of EVIO pilot plant. The evaluation of the basic parameters of the installation has been done using computer models.