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Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
N.I. Arkhipov, V.P. Bakhtin, S.M. Kurkin, V.M. Safronov, D.A. Toporkov, S.G. Vasenin, H. Wuerz, A.M. Zhitlukhin
Fusion Science and Technology | Volume 35 | Number 1 | January 1999 | Pages 131-135
Oral Presentations | doi.org/10.13182/FST99-A11963837
Articles are hosted by Taylor and Francis Online.
Process of interaction of intense plasma fluxes up to 10 MW/cm2 with solid targets was studied experimentally. It was shown that a dense plasma layer arises near target surface and protects the target from direct effect of an incoming high temperature plasma. Spatial distribution and temporal behavior of the shielding layer depend on the target materials. For a high Z materials (tungsten, copper, stainless steel) dense plasma layer is localized near the surface during all time of the interaction. For a low Z materials (graphite, boron nitrid, plexiglass, aluminium) low dense plasma cloud – “corona” rapidly expands toward incoming plasma flow along the magnetic field lines. The experiments demonstrated effective shielding of the different materials surface from excessive evaporation. Bulk energy of incoming plasma is converted into SXR radiation in near surface layer for a high Z materials and, partially, into target plasma heating for a low Z materials. Measured parameters of plasma shield are used as a benchmark in developing numerical codes to predict a real damage for ITER divertor plates due to hard disruptions.