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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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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.
T. Kammash
Nuclear Science and Engineering | Volume 7 | Number 5 | May 1960 | Pages 425-434
Technical Paper | doi.org/10.13182/NSE60-A25740
Articles are hosted by Taylor and Francis Online.
The elastic-plastic deformation of a tube subjected to radially uniform heat generation is considered using Tresca's yield function, its associated flow rule, and a linear work-hardening law. The tube is assumed to be in the state of plane strain and all the elastic and thermal parameters are taken to be temperature independent. For a uniform heat source Q, which increases monotonically with time and which has an insulated inner surface, yielding commences at the inner boundary and propagates outward upon further thermal loading. Immediately after initiation of yield, a plastic region (inner) and an elastic region (outer) are formed with the tangential stress as the intermediate principal stress in both regions. The maximum strength of a heat source, QM, to which a tube may be subjected is taken to correspond to that value of Q which makes the tube almost entirely plastic. This value of Q is computed for several graphite tubes of different thicknesses and then compared with an experimentally obtained QF which corresponds to total failure (fracture) of these tubes. A value of approximately 2.5 is obtained for QF/QM for tubes of moderate thicknesses. Furthermore, the ratio QF/QM remains practically constant as tube thickness increases. Agreement between theory and experiment especially in depicting the dependence of failure load on tube thickness and temperature gradient is considered excellent in light of the many assumptions made. The application of this theory to the design of nuclear reactor fuel elements is also pointed out.
