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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
L.L. Lengyel, K. Borrass
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 1760-1765
Plasma Heating, Impurity Control, and Fueling | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40015
Articles are hosted by Taylor and Francis Online.
The fueling requirements of fusion reactors are analyzed on the basis of a recent assessment performed for NET (Next European Torus). Results of penetration depth calculations applied to single pellets under thermonuclear plasma conditions are described. Data corresponding to the commonly used neutral gas shielding ablation model and a magnetic shielding approximation are compared. The pellet size and pellet velocity requirements for central fueling are established. Scenario calculations are performed with the help of a 1D tokamak transport code. The pellet size, pellet velocity, and injection frequency requirements for continuous fueling or, for example, ignition with the help of pellets are obtained. The effect of runaway electrons, NB ions and alpha particles is estimated by calculating the ablation rates caused by these particles in fusion plasmas and comparing them with the ablation rate induced by thermal electrons.
