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The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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Fusion Science and Technology
Latest News
Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
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.