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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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Latest News
Fire reported at Zaporizhzhia as Ukrainian troops advance toward Russia’s Kursk plant
Thick, black smoke pouring from one of the cooling towers at Ukraine’s Zaporizhzhia nuclear power plant over the weekend raised alarm about safety at the facility as the military conflict with Russia continues.
On-site staff from the International Atomic Energy Agency witnessed the smoke and reported hearing multiple explosions at Zaporizhzhia, which is the largest nuclear plant in Europe and one of the largest worldwide.
H. E. McCoy, R. L. Beatty, W. H. Cook, R. E. Gehlbach C. R. Kennedy, J. W. Koger, A. P. Litman, C. E. Sessions, J. R. Weir
Nuclear Technology | Volume 8 | Number 2 | February 1970 | Pages 156-169
Reactor | doi.org/10.13182/NT70-A28622
Articles are hosted by Taylor and Francis Online.
Operating experience with the Molten-Salt Reactor Experiment (MSRE) has demonstrated the excellent compatibility of the graphite-Hastelloy-N-fluoride salt system at 650°C. Several improvements in materials are needed for a molten-salt breeder reactor with a basic plant life of 30 years; specifically: Hastelloy-N with improved resistance to embrittlement by thermal neutrons; graphite with better dimensional stability in a fast neutron flux; graphite that is sealed to obtain a surface permeability of <10-8 cm2/sec; and a secondary coolant that is inexpensive and has a melting point of ∼400°C. A brief description is given of the materials work in progress to satisfy each of these requirements.