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Fusion Science and Technology
A day in the life of the nuclear community
The November issue of Nuclear News is focused on the individuals who make up our nuclear community.
We invited a small group of those individuals to tell us about their day-to-day work in some of the many occupations and applications of nuclear science and technology, and they responded generously. They were ready to tell us about the part they play, together with colleagues and team members, in supplying clean energy, advancing technology, protecting safety and health, and exploring fundamental science.
In these pages, we see a community that can celebrate both those workdays that record progress moving at a steady pace and the exceptional days when a goal is reached, a briefing is delivered, a contract goes through, a discovery is made, or an unforeseen challenge is overcome.
The Nuclear News staff hopes that you enjoy meeting these members of our community—or maybe get reacquainted with friends—through their words and photos.
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 | dx.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.