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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.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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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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.
Paul W. Humrickhouse, Brad J. Merrill, Su-Jong Yoon, Lee C. Cadwallader
Fusion Science and Technology | Volume 75 | Number 8 | November 2019 | Pages 973-1001
Technical Paper | doi.org/10.1080/15361055.2019.1658464
Articles are hosted by Taylor and Francis Online.
In this work we consider some of the safety implications of using liquid metal (LM) plasma-facing components (PFCs) in future fusion reactors. Candidate LMs include lithium, tin, and tin-lithium alloys, and we consider a modified Fusion Nuclear Science Facility design with a dual-cooled lead-lithium blanket and fast-flowing LM first wall and divertor consisting of each of these aforementioned metals. Tin and tin-lithium PFCs are found to have little impact on the potential source terms, including tritium and activation product releases during an accident as well as tritium permeation losses during normal operation, relative to the lead-lithium blanket. For a lithium PFC, chemical reactivity and high tritium inventories are additional concerns. We outline some necessary safety precautions for lithium systems and review the relevant operating experience of sodium-cooled fission reactors. Design constraints to keep the tritium inventory low in such a lithium system are outlined, including in the tritium extraction system, which will have to rely on different techniques than envisioned for other LMs such as PbLi, Sn, and SnLi, which have a much lower tritium solubility than lithium. Development of such extraction systems is significant research and development needed prior to deployment of lithium PFCs.