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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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Nuclear Science and Engineering
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Nuclear Technology
Fusion Science and Technology
Latest News
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.
D. C. Wilson, P. A. Bradley, S. R. Goldman, N. M. Hoffman, R. W. Margevicius, R. B. Stephens, R.E.Olson
Fusion Science and Technology | Volume 38 | Number 1 | July 2000 | Pages 16-21
Technical Paper | Thirteenth Target Fabrication Specialists’ Meeting | doi.org/10.13182/FST00-A36109
Articles are hosted by Taylor and Francis Online.
Recent beryllium capsule designs have focussed on the lower temperatures and laser powers expected before the NIF laser reaches its full capability, 192 beams, 500TW, and 1.8MJ. First, several new designs are given with peak radiation temperatures for 250 to 280 eV. A 250eV design uses 2% oxygen dopant instead of 0.9% copper. Second, a radiography study of planar joints in S200D beryllium using a Cu, Au, Ag, Al, or Au/Cu braze quantified the diffusion away from the joint. LASNEX calculations show that Cu joint perturbations grow to large enough amplitude to preclude ignition. However by allowing the copper to diffuse twice as far as in these experiments (e.g. by holding at braze temperature longer), the joint calculates to be acceptable, and the capsule gives full yield. Aluminum diffuses extremely far from the joint, almost uniformly in the sample. Third, a capsule with a high Z shell and beryllium ablator calculates to ignite. As expected its ignition threshold is lower, about 70% of the implosion velocity for a capsule like the Be330. The extra tamping of DT bum by a 6 μm tungsten shell increases the yield from 17 to 32 MJ. The capsule radiates 3 MJ of this yield as X-rays. Unfortunately the capsule is more sensitive to DT ice roughness than the Be330 design, failing at 0.6μm roughness.