ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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.
Enrico Lucon, Rik-Wouter Bosch, Lorenzo Malerba, Steven Van Dyck, Marc Decréton
Fusion Science and Technology | Volume 47 | Number 4 | May 2005 | Pages 895-900
Technical Paper | Fusion Energy - Fusion Materials | doi.org/10.13182/FST05-A801
Articles are hosted by Taylor and Francis Online.
For the last 20 years, fusion material programs in Europe, Japan and US have been focused on developing Reduced Activation Ferritic/Martensitic (RAFM) steels as prominent structural materials. In the European Union, within the Long Term Programme of EFDA (European Fusion Development Agreement), considerable effort has been spent by several scientific institutions for the characterization and optimization of the European reference RAFM steel (EUROFER97). Within the Belgian Nuclear Centre (SCKCEN), an integrated approach to the characterization of EUROFER97 is being consistently applied; this includes: neutron irradiations in the BR2 reactor and subsequent characterization of the unirradiated and irradiated mechanical properties (tensile, impact and fracture toughness tests); investigation of environmentally assisted cracking (more specifically, study of the influence of irradiation damage on both EAC and embrittlement in Pb-Li alloys); multiscale modelling of radiation effects and specific effects on Fe-Cr systems, using methods which range from the atomic level (MD - Molecular Dynamics) to the mesoscopic level (KMC - Kinetic Monte Carlo). This paper will provide a general overview of the above mentioned investigations, as well as highlights of the most significant results obtained in the different fields of activity.