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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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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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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Latest News
Tank waste operations resume at Idaho’s IWTU
The Department of Energy’s Office of Environmental Management announced yesterday that waste processing operations have resumed at the Integrated Waste Treatment Unit (IWTU) at the Idaho National Laboratory Site. The resumption of operations follows the completion of two maintenance campaigns at the radioactive liquid waste treatment facility.
K. Katayama et al.
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 561-564
Technical Paper | Tritium Science and Technology - Materials Interaction and Permeation | doi.org/10.13182/FST05-A987
Articles are hosted by Taylor and Francis Online.
Release behavior of hydrogen isotopes from the graphite tiles used in JT-60U was observed using the thermal desorption method where temperature was stepwise elevated to 300, 600 and 1000 °C. When first wall tile was left under helium atmosphere at 600 °C for 8 hours, about 40 % of total amount of hydrogen and deuterium retained in the tile was released, although only a small amount of hydrogen isotopes was released at 300 °C, which is the base temperature of inner wall of JT-60U. This indicates that a higher temperature of inner wall causes hydrogen retention to reduce considerably. When the graphite tiles were exposed to hydrogen at 1000 °C, the release of deuterium and tritium was enhanced. It is considered that the deuterium and tritium left in the graphite tile was released by the isotope exchange reaction. In order to remove almost all deuterium or tritium from the graphite tile without combustion of graphite, isotope exchange method at high temperature is effective. It was found that the amount of hydrogen retained in the graphite tile was much larger than that of deuterium. This indicates that a large amount of deuterium trapped in the tiles during deuterium discharge experiments was replaced with hydrogen during hydrogen discharge experiments. Additionally, depth profiles of hydrogen isotope are discussed from the obtained release curves.