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Division Spotlight
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.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Fusion Science and Technology
Latest News
College students help develop waste measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
N. A. Uckan, D. E. Post, J. C. Wesley, ITER JCT, ITER Home Teams, ITER Physics Expert Groups
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 371-376
International Thermonuclear Experimental Reactor (ITER) | doi.org/10.13182/FST98-A11963642
Articles are hosted by Taylor and Francis Online.
The physics knowledge relevant to the design of a reactor-scale tokamak—the ITER Physics Basis—has recently been assessed by the ITER JCT, the ITER Home Teams, and the ITER Physics Expert Groups. Physics design guidelines and methodologies for projecting plasma performance in ITER and reactor tokamaks are developed from extrapolations of various characterizations of the database for tokamak operation and of the understanding that its interpretation provides. Both “conventional” and “advanced tokamak” operating modes are considered. The overall device parameters for ITER are found to be consistent with these guidelines. The plasma performance attainable in ITER is affected by many physics issues, including energy confinement, L-to H and H-to-L-mode power transition thresholds, MHD stability/beta limit, density limit, disruptions, helium removal, impurity content, etc. Design basis and guidelines are provided in each of these areas, along with sensitivities and/or uncertainties involved.