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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
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.
K. H. Beckurts
Nuclear Science and Engineering | Volume 2 | Number 4 | July 1957 | Pages 516-522
Technical Paper | doi.org/10.13182/NSE57-A25417
Articles are hosted by Taylor and Francis Online.
The pulse method has been applied to problems of neutron diffusion in graphite. By measuring the decay constant of the neutron flux emanating from various graphite pile geometries, the diffusion coefficient and the absorption cross section can be determined with great precision. In comparison to an exponential experiment, the quantity of graphite necessary for an accurate determination of the diffusion length can be considerably reduced. The finite geometry of the moderator gives rise to a diffusion-cooling effect on the neutron equilibrium temperature which can be understood quantitatively by a direct measurement of the heat transfer from the neutron gas to the lattice. In the second part of the work, the pulse method is used to determine the influence of eccentric control rods on the buckling of a cylindrical reactor model.
