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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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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Fusion Science and Technology
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.
Jean Boscary, Masanori Araki, Satoshi Suzuki, Koichiro Ezato, Masato Akiba
Fusion Science and Technology | Volume 35 | Number 3 | May 1999 | Pages 289-296
Technical Paper | doi.org/10.13182/FST99-A82
Articles are hosted by Taylor and Francis Online.
The purpose of the International Thermonuclear Experimental Reactor (ITER) divertor, which is located at the bottom of the vacuum vessel, is to exhaust impurities and their power from the plasma. Divertor plates function to withstand and to remove a steady-state surface heat flux of 5 MW/m2 and a transient peak heat flux up to 20 MW/m2 for 10 s on the side that faces the plasma. These demanding heat loads require active cooling by a pressurized subcooled flow of water as well as the development of a high-performance cooling channel to avoid burnout. Previous experiments showed that a screw tube, which is a tube whose inner surface is machined like a nut, is an efficient means of removing high heat fluxes. New experiments have been carried out with a B 0205 M10 type of screw copper tube. The average inner diameter, i.e., at the midheight of the fin, is 10 mm, and the outer diameter is 14 mm. Different pitches have been investigated: 1.5, 1.25, 1, and 0.75 mm. Incident critical heat fluxes (ICHFs) between 25 and 47 MW/m2 have been reached for local pressures ranging from 0.9 to 2.2 MPa, inlet temperatures from 17 to 33°C, and axial velocities from 3.6 to 14 m/s. ICHF increases as axial velocity increases and depends slightly on local pressure. Experimental results confirm the potentialities of the screw tube as a reliable geometry for fusion cooling tubes.