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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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2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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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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Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
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.