ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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Nuclear Science and Engineering
January 2025
Nuclear Technology
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.
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.