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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
R. Matera, M. Merola
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1873-1879
Plasma-Facing Component | doi.org/10.13182/FST92-A29992
Articles are hosted by Taylor and Francis Online.
The paper presents the conceptual study of an innovative divertor plate for the physical phase of the ITER/NET reactor. The main distinguishing feature of the new concept is the use of a single material, a Carbon Fibre reinforced Carbon (CFC) composite with ultra-high-thermal conductivity carbon fibres, for the whole structure, i.e. for the protective armour, heat sink and cooling channels. The main potential advantages of such a solution are perceived to be: elimination of the severe joint-interface problems inherent to other multimaterial solutions; weak interaction with runaway electrons; low-activation properties; reduction of mechanical stresses induced by electromagnetic transient. Moreover, the use of helium as a coolant leads to the following additional advantages: avoidance of the risk of burn-out; flexibility towards different operating scenarios; ease of baking at high temperature; lower tritium inventory in the CFC material; avoidance of the sharp pressure rise in cooling circuit because of water evaporation due to runaway electron impact. The thermal performance assessment shows that the maximum surface temperature can be kept below the threshold for radiation enhanced sublimation with comparable pumping power with that required by water cooling with turbulence promoters. After this study, which has to be considered as a first step in the iterative process for the development of a new component, the issue of the manufacturing feasibility in close collaboration with the composite industry will be addressed.