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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.
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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
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
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.
P. W. Fisher, M. J. Gouge
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 515-520
Fueling and Tritium Handling Technology (Poster Session) | doi.org/10.13182/FST98-A11963664
Articles are hosted by Taylor and Francis Online.
As part of the International Thermonuclear Experimental Reactor (ITER) plasma fueling development program, Oak Ridge National Laboratory has fabricated a pellet injection system to test the mechanical and thermal properties of extruded tritium. This repeating single-stage, pneumatic, Tritium-Proof-of-Principle Phase II (TPOP-II) Pellet Injector has a piston-driven mechanical extruder and is designed to extrude and accelerate hydrogenic pellets sized for the ITER device. Tritium and deuterium-tritium (D-T) pellets have been produced in experiments at the Los Alamos National Laboratory Tritium Systems Test Assembly. About 38 g of tritium was used in the experiment. This paper presents results of the TPOP-II extrusion experiments. These extrusion experiments indicate that both T2 and D-T will require higher extrusion forces than D2 by about a factor of 2 and that the flow of the material may be characterized by static and dynamic shear strengths.
