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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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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Fusion Science and Technology
Latest News
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.
J. W. Coenen, B. Bazylev, S. Brezinsek, V. Philipps, T. Hirai, A. Kreter, J. Linke, G. Pintsuk, G. Sergienko, A. Pospieszczyk, T. Tanabe, Y. Ueda, U. Samm, The TEXTOR Team
Fusion Science and Technology | Volume 61 | Number 2 | February 2012 | Pages 129-135
Technical Paper | First Joint ITER-IAEA Technical Meeting on Analysis of ITER Materials and Technologies | doi.org/10.13182/FST12-A13378
Articles are hosted by Taylor and Francis Online.
Behavior and characteristics of tungsten materials under impinging high heat fluxes are investigated. Experiments with inertially - not actively - cooled samples have been carried out in the plasma edge of the TEXTOR tokamak to study the changes of material properties such as grain size and abundance of voids or bubbles. In addition, the effects of electron beam impact regarding subsequent W power handling have been studied in view of future devices.The parallel heat flux at the radial position in TEXTOR impinging on the plasma-facing components (PFCs) ranges around q[parallel] [approximately] 45 MW/m2 allowing samples to be exposed at an impact angle of 35 deg to 20 to 30 MW/m2. Melt layer motion perpendicular to the magnetic field is observed following a Lorentz force originating from thermoelectric emission of the hot W sample. Up to 3 g of molten W are redistributed forming hill-like structures at the plasma-connected edge of the sample. The typical melt layer thickness is 1.0 to 1.5 mm. Those hills are, due to the changes in the local geometry, particularly susceptible to even higher heat fluxes of up to the full q[parallel]; hence, locally the temperature of W can reach up to 6000 K, and thus boiling can occur.In terms of material degradation, several aspects are considered: formation of leading edges by redistributed melt, bubble formation, and recrystallization. Bubbles are occurring in sizes between 1 and 200 m while recrystallization increases the grain size up to 1.5 mm. The power-handling capabilities are severely degraded by all those aspects. Melting of tungsten in future devices is highly unfavorable and needs to be avoided especially in light of uncontrolled transients and possible unshaped PFCs.Predamaged samples from the TEXTOR exposures have also been exposed in the JUDITH 1 facility under transient heat loads (up to [approximately]1 GW/m2, energy impact: 36 MWm-2s1/2). The samples show an unfavorable increase in the ductile-to-brittle transition temperature. In addition, surface cracks lose their directionality recrystallizing toward a more isotropic state from the manufactured monodirectional state. The increased grain size leads to a more brittle behavior under transient thermal loads with respect to crack progression.