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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Retrieval of nuclear waste canisters from a borehole
Borehole disposal of spent nuclear fuel (SNF) and high-level waste (HLW) uses off-the-shelf directional drilling technology developed and commercialized by the oil and gas sectors. It is a technology that has been gaining traction in recent years in the nuclear industry. Disposal can be done in one or more boreholes (including an array) drilled into suitable sedimentary, igneous, or metamorphic host rocks. Waste is encapsulated in specialized corrosion-resistant canisters, which are placed end to end in disposal sections of relatively small-diameter boreholes that have been cased and fluid-filled. After emplacement, the vertical access hole is plugged and backfilled as an engineered barrier.
F. Ono, S. Tanaka, M. Yamawaki
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1964-1967
Material and Tritium | doi.org/10.13182/FST92-A30008
Articles are hosted by Taylor and Francis Online.
Sorption of tritiated water on organic materials such as rubber, linoleum and acrylic resin, and subsequent desorption by wet gas purging were studied. Sorption amount was found to increase slightly with contact time. Adsorption coefficient, which was defined as the ratio of adsorption amount to the initial HTO concentration in the exposed gas phase, was compared with reported values on various materials. From the decrease of tritium concentration in the swept gas during desorption by wet gas purging, desorption rate constants were calculated. They were in the order of 10−2 min−1 and were found to decrease with the contact time.