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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
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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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
ARPA-E announces $40 million to develop transmutation technologies for UNF
The Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E) announced $40 million in funding to develop cutting-edge technologies to enable the transmutation of used nuclear fuel into less-radioactive substances. According to ARPA-E, the new initiative addresses one of the agency’s core goals as outlined by Congress: to provide transformative solutions to improve the management, cleanup, and disposal of radioactive waste and spent nuclear fuel.
Tristan S. Hunnewell, Kyle L. Walton, Sangita Sharma, Tushar K. Ghosh, Robert V. Tompson, Dabir S. Viswanath, Sudarshan K. Loyalka
Nuclear Technology | Volume 198 | Number 3 | June 2017 | Pages 293-305
Technical Paper | doi.org/10.1080/00295450.2017.1311120
Articles are hosted by Taylor and Francis Online.
Type 316L stainless steel (SS 316L) is a candidate material for the reactor core barrel and selected internal components for high (and very high) temperature gas reactors. An apparatus constructed in accordance with the standard ASTM C835-06 was used for measuring total hemispherical emissivity of this material for the following surface conditions: (1) “as-received” from the manufacturer, (2) sandblasted with alumina beads, (3) sandblasted and coated with IG-11 nuclear-grade graphite powder, and (4) oxidized in air at 973 K for different durations. The emissivity of the as-received samples increased from 0.25 at 436 K to 0.36 at 1166 K. Sandblasting with 60-grit–sized alumina beads increased the emissivity from 0.32 to 0.44 in the temperature range from 561 to 1095 K. The emissivity continued to increase with sandblasting with 120- and 220-grit alumina beads, despite decrease in surface area associated with the more finely sized alumina beads. The coating of IG-11 graphite powder further increased the emissivity of the sandblasted surfaces. Following a similar trend, the IG-11–coated surfaces sandblasted by 120- and 220-grit alumina had an emissivity from 0.42 at 540 K to 0.57 at 1075 K. Electron micrographs showed more deposition of IG-11 powder on the 120- and 220-grit sandblasted surfaces. Oxidation in air at 973 K for 5 min also increased the emissivity of SS 316 L. Oxidations for 10 and 15 min provided an additional increase, but it was not as significant. Analysis indicates that spallation of oxide layer occurred between 10 and 15 min oxidation. This is consistent with studies on the time variation of total normal emissivity of SS 316L for oxidation at similar temperature.