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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.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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
Latest News
A more open future for nuclear research
A growing number of institutional, national, and funder mandates are requiring researchers to make their published work immediately publicly accessible, through either open repositories or open access (OA) publications. In addition, both private and public funders are developing policies, such as those from the Office of Science and Technology Policy and the European Commission, that ask researchers to make publicly available at the time of publication as much of their underlying data and other materials as possible. These, combined with movement in the scientific community toward embracing open science principles (seen, for example, in the dramatic rise of preprint servers like arXiv), demonstrate a need for a different kind of publishing outlet.
François Ryter, Albrecht Stäbler, Giovanni Tardini
Fusion Science and Technology | Volume 44 | Number 3 | November 2003 | Pages 618-635
Technical Paper | ASDEX Upgrade | doi.org/10.13182/FST03-A403
Articles are hosted by Taylor and Francis Online.
The studies carried out in ASDEX Upgrade on transport in conventional scenarios are presented. The well-known property of tokamak temperature profiles being resilient is investigated in and interpreted, for both ions and electrons, as due to the existence of an inverse critical gradient length below which transport is low and above which it increases. Experiments in H-mode with different heating power deposition profiles were carried out. Simulation results of a variety of H-mode plasmas with three different transport models based on the physics assumptions that include the existence of such a threshold confirm this hypothesis. However, the profiles are not extremely stiff and can significantly deviate from the critical value. Electron heat transport was investigated in various experiments using electron cyclotron heating combining steady-state and power modulation. A variation of the electron heat flux while keeping the edge flux constant allows measurement of the threshold and the properties of electron transport. These resilience properties lead to a correlation between core and edge and to a dependence of global confinement on the pedestal energy. This is quantified in the analyses of a database that yield expressions linking edge and global confinement.