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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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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, D. Lodi, J. Marian, A. Gonzalez Plata, M. Salvador, L. Colombo, M. J. Caturla, T. Diaz de la Rubia
Fusion Science and Technology | Volume 43 | Number 3 | May 2003 | Pages 384-392
Technical Paper | Chambers and Chamber Wall Protection Methods | doi.org/10.13182/FST03-A282
Articles are hosted by Taylor and Francis Online.
New results are presented on the time-dependent neutron intensities and energy spectra from compressed inertial fusion energy (IFE) targets and in structural Fe walls behind typical IFE chamber protection schemes. Protection schemes of LiPb and Flibe have been considered with two different thicknesses, and neutron fluxes in the outer Fe layer as a function of the time from target emission are given. Differences between the two solutions are noted and explained, and the effect of thickness is quantitatively shown. Time-dependent defect characterization of the Fe layer under pulse irradiation is presented. A new well-established multiscale modeling procedure injects, at the appropriate dose rate, damage cascades in a kinetic Monte Carlo lattice (microscopic) to study defect diffusion, clustering, and disintegration. The differences with a continuous irradiation for a still low fluence of irradiation are presented. Experimental validation of a multiscale modeling approach has been recognized and proposed in the Spanish VENUS-II project by using Fe ions on pure and ultrapure Fe. To study similar problems in SiC, new tools are needed to quantify the kinetic defects; results leading to the validation of a new tight binding molecular dynamics code for SiC are presented.
