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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Penn State and Westinghouse make eVinci microreactor plan official
Penn State and Westinghouse Electric Company are working together to site a new research reactor on Penn State’s University Park, Pa., campus: Westinghouse’s eVinci, a HALEU TRISO-fueled sodium heat-pipe reactor. Penn State has announced that it submitted a letter of intent to host and operate an eVinci reactor to the Nuclear Regulatory Commission on February 28 and plans to engage with the NRC on specific siting decisions. Penn State already boasts the Breazeale reactor, which began operating in 1955 as the first licensed research reactor at a university in the United States. At 70, the Breazeale reactor is still in operation.
J. H. Kittel, S. Greenberg, S. H. Paine, J. E. Draley
Nuclear Science and Engineering | Volume 2 | Number 4 | July 1957 | Pages 431-449
Technical Paper | doi.org/10.13182/NSE57-A25408
Articles are hosted by Taylor and Francis Online.
Three corrosion-resistant uranium-base alloys, U-3 weight per cent Nb, U-5 weight per cent Zr-1½ weight per cent Nb, and U-3.8 weight per cent Si (U3Si) were irradiated to burnups of 0.1 atomic per cent or less. Observations were made of irradiation-induced length changes in specimens of the alloys as influenced by the method of fabrication and heat treatment, and of changes in aqueous corrosion resistance resulting from irradiation. It was found that the uranium-niobium alloy was unsuitable from the standpoint of dimensional and surface stability, and its corrosion resistance was destroyed by irradiation. The uranium-zirconium-niobium alloy could be nominally stabilized under irradiation and its corrosion resistance was destroyed by between 0.046 and 0.074 atomic per cent burnup. The uranium-silicon alloy was relatively stable under irradiation and showed no increase in corrosion rate at 290°C after 0.090 atomic per cent burnup, although cracking occurred after several days corrosion testing.
