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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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Nuclear Science and Engineering
March 2025
Nuclear Technology
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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.
W. Primak, L. H. Fuchs
Nuclear Science and Engineering | Volume 2 | Number 1 | February 1957 | Pages 49-56
doi.org/10.13182/NSE57-A15572
Articles are hosted by Taylor and Francis Online.
A method for using a saturating property to formulate a linear dosage scale is developed. The method is applied to the determination of the radiation damage rate for graphite in a nuclear reactor using the per cent decrease in electrical conductivity as the property. The damage rates in a number of irradiation facilities of the CP-3, CP-3′, and X-10 reactors are given. It is conclusively shown that the thermal neutron flux cannot be used to indicate the damage rate, for the one can be varied by more than an order of magnitude with respect to the other.
