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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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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
November 2024
Latest News
Texas-based WCS chosen to manage U.S.-generated mercury
A five-year, $17.8 million contract has been awarded to Waste Control Specialists for the long-term management and storage of elemental mercury, the Department of Energy’s Office of Environmental Management announced on November 21.
N. S. Klimov, V. L. Podkovyrov, A. M. Zhitlukhin, A. D. Muzichenko, D. V. Kovalenko, A. B. Putrik, I. B. Kupriyanov, R. N. Giniyatulin, A. A. Gervash, V. M. Safronov
Fusion Science and Technology | Volume 66 | Number 1 | July-August 2014 | Pages 118-124
Technical Paper | doi.org/10.13182/FST13-759
Articles are hosted by Taylor and Francis Online.
The beryllium (Be) plasma-facing components (PFCs) of the ITER first wall (FW) were tested in the plasma gun QSPA-Be under pulsed plasma heat loads of 0.5-ms duration relevant to those expected in ITER during transient plasma events (edge-localized modes and disruptions). The experiments were performed for different Be grades (Russian TGP-56FW and US S65-C). The measured Be melting threshold decreases from 0.5 MJm−2 down to 0.4 MJm−2 with Be initial temperature increasing in the range of 250–500 °C. Under plasma heat loads on the exposed surface below the melting point the Be PFC erosion was mainly due to melting of the plasma-facing and lateral edges of the Be tiles. Under plasma heat loads above the melting point the Be PFC erosion was mainly due to intense melt layer movement and splashing. The Be melt layer behavior at 0.5 and 1.0 MJm−2 is similar to early investigated W melt layer behavior at higher heat loads of 1.0 and 1.5 MJm−2 correspondingly. Unlike W the Be erosion rate significantly increases with initial temperature in the range of 250–500 °C. These experimental observations are supported by calculation of temperature dynamics and melt layer thickness dynamics.