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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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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Winfried Kernbichler
Fusion Science and Technology | Volume 21 | Number 4 | July 1992 | Pages 2297-2306
Technical Paper | Special Issue on D-He Fusion / D-3He/Fusion Reactor | doi.org/10.13182/FST92-A29723
Articles are hosted by Taylor and Francis Online.
The intrinsic potential of a field-reversed configuration (FRC) for high-beta operation (beta values in the range of 50 to 100%) stimulates much interest in this device as an attractive candidate for a compact fusion reactor with high power density. Several additional benefits, e.g., the cylindrical geometry of the concept, the simplicity of the magnetic system, the simply connected plasma, the low synchrotron radiation, the divertor action of the open field lines, and the possibility for direct energy conversion of the charged-particle flow, justify a closer look at the benefits and problems of FRCs. The emphasis here is on operation with D-3He fuel under reactor-relevant conditions, whereas deuterium-tritium (D-T) is taken as a reference case. The reasons for that choice are that (a) D-3He offers intrinsic advantages over D-T in neutron production and radioactive inventory and (b) the high-beta regime of an FRC matches ideally some of the requirements for D-3He operation. A steady-state version of an FRC is considered to be more attractive than its pulsed counterpart. Frequent startup to high temperatures would be particularly detrimental for D-3He, where startup scenarios seem to rely either on the transition from D-T to D-3He, with unavoidable strong tritium contamination, or on high-power neutral beam injection.