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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
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
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
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Judge temporarily blocks DOE’s move to slash university research funding
A group of universities led by the American Association of Universities (AAU) acted swiftly to oppose a policy action by the Department of Energy that would cut the funds it pays to universities for the indirect costs of research under DOE grants. The group filed suit Monday, April 14, challenging a what it termed a “flagrantly unlawful action” that could “devastate scientific research at America’s universities.”
By Wednesday, the U.S. District Court judge hearing the case issued a temporary restraining order effective nationwide, preventing the DOE from implementing the policy or terminating any existing grants.
V. Kapychev, V. Gorokhov, D. Davydov, V. Demidov, Yu. Kazennov, V. Tebus, V. Frolov, A. Shikov, N. Shishkov, V. Kovalenko, A. Lopatkin, A. Marachev, V. Shishkin, Yu. Strebkov, L. Men'kin, A. Zyryanov
Fusion Science and Technology | Volume 39 | Number 1 | January 2001 | Pages 45-53
Technical Paper | doi.org/10.13182/FST01-A150
Articles are hosted by Taylor and Francis Online.
A model of a ceramic breeding zone has been designed and manufactured for testing in the IVV-2M fission reactor. The model contains both lithium orthosilicate and beryllium spheroid particles 1 to 2 mm in diameter. The structural material is ferritic-martensitic stainless steel. In addition, a mockup of the model for verification of neutronics calculation methods has been designed and manufactured. A special facility (Functional In-Reactor Investigations of Tritium-Breeding Models) has been designed, fabricated, and assembled at the reactor for studying the kinetics of tritium extraction from the ceramic material under irradiation. Neutronic and thermo-hydraulic calculations and an initial measurement of tritium release from the model under reactor irradiation have been performed.
