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Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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Latest News
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.
T. Ishida, T. Hayashi, M. Yamada, T. Suzuki, K. Okuno
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 926-930
Fuel Cycle and Tritium Technology | doi.org/10.13182/FST96-A11963057
Articles are hosted by Taylor and Francis Online.
In order to develop the more compact and more cost-effective tritium removal system for the fusion reactor, the new system of using gas separation membrane has been studied in Tritium Process Laboratory (TPD/Japan Atomic Energy Research Institute (JAERI). To apply the scaled polyimide membrane module (hollow filament type) to the secondary confinement system, the basic-tritium recovery performance was summarized as a module itself from N2, air, Ar mixture, and recoveral performance was well demonstrated from existing glovebox (1.4 m3 : GB). The tritium recovery performance of the membrane module was well analyzed as a cross flow model, and removal from actual GB results was well simulated by the stand-alone performance data. Using this membrane module performance, new detritiation system was designed for the secondary confinement (GB).