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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Latest News
NWMO to select Canadian repository site this year
Canada’s Nuclear Waste Management Organization, a not-for-profit organization responsible for the long-term management of the country’s intermediate- and high-level radioactive waste, is set to select a site for a deep geologic repository by the end of the year.
M. Z. Youssef, P. Batistoni, L. Patrizzi, T. Wareing, I. M. Davis
Fusion Science and Technology | Volume 52 | Number 4 | November 2007 | Pages 801-806
Technical Paper | Nuclear Analysis and Experiments | doi.org/10.13182/FST07-A1589
Articles are hosted by Taylor and Francis Online.
The calculation accuracy of the newly developed 3D discrete ordinates code, Attila, is benchmarked by comparing its prediction to the measured data in two mockups bombarded by 14 MeV neutron source of the FNG facility located at Frascati, Italy. The results are also compared to those based on MCNP Monte Carlo code for the same measured reactions. The experimental mock-ups simulate parts of ITER in-vessel components, namely, the tungsten (W) mockup and the ITER shielding blanket. The first mockup was used to validate W data as a material for plasma facing component. A streaming path was introduced in the second configuration. The objective of this paper is to benchmark Attila code to determine its adequacy for fusion application. Another objective is to compare results based on two distinctive 3D calculation tools using the same nuclear data, FENDL2.1, and the same response function (IRDF-90) for measured data. The results of these comparisons are reported in this paper.