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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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Fusion Science and Technology
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A more open future for nuclear research
A growing number of institutional, national, and funder mandates are requiring researchers to make their published work immediately publicly accessible, through either open repositories or open access (OA) publications. In addition, both private and public funders are developing policies, such as those from the Office of Science and Technology Policy and the European Commission, that ask researchers to make publicly available at the time of publication as much of their underlying data and other materials as possible. These, combined with movement in the scientific community toward embracing open science principles (seen, for example, in the dramatic rise of preprint servers like arXiv), demonstrate a need for a different kind of publishing outlet.
J. M. Perlado, E. Domínguez, D. Lodi, L. Malerba, J. Marian, J. Prieto, M. Salvador, T. Díaz de la Rubia, E. Alonso, M. J. Caturla, L. Colombo
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 579-584
Fusion Materials | doi.org/10.13182/FST01-A11963299
Articles are hosted by Taylor and Francis Online.
The change in SiC properties under neutron irradiation is being experimentally assessed but it is actually far from being well understood. Using Molecular Dynamics (MDCASK-DENIM/LLNL), we show the existence of recombination barriers (metastable defects), and how they affect the cascade analysis. Displacement cascades have been systematically studied and the different role of both sublattices examined. Low-temperature amorphization by damage accumulation has been successfully simulated using MD in accordance with experiments, allowing the understanding (not possible from experiments) of the atomistic sequence of damage. We are also developing new methodologies (tight binding MD) to prove the adequacy of the interatomic potential to describe energetic of configurations needed for diffusion in SiC. The neutron source from target is obtained with time resolution, together with responses after transport in the IFE reactor. The comparison of different primary knock-on atom (PKA) energy spectra from different fusion reactors is given, which is a basic information for displacement cascade analysis. Those spectra are a direct consequence of the neutron spectra in the material (depending on protection). Supported by recent work on atomistic level, the effect of pulsed irradiation was concluded. The time between pulses has a key role in the annealing process of defects. The comparison with average continuous irradiation, and the different behaviour for vacancies and interstitials, are highlighted.