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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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2021 Student Conference
April 8–10, 2021
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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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NC State celebrates 70 years of nuclear engineering education
An early picture of the research reactor building on the North Carolina State University campus. The Department of Nuclear Engineering is celebrating the 70th anniversary of its nuclear engineering curriculum in 2020–2021. Photo: North Carolina State University
The Department of Nuclear Engineering at North Carolina State University has spent the 2020–2021 academic year celebrating the 70th anniversary of its becoming the first U.S. university to establish a nuclear engineering curriculum. It started in 1950, when Clifford Beck, then of Oak Ridge, Tenn., obtained support from NC State’s dean of engineering, Harold Lampe, to build the nation’s first university nuclear reactor and, in conjunction, establish an educational curriculum dedicated to nuclear engineering.
The department, host to the 2021 ANS Virtual Student Conference, scheduled for April 8–10, now features 23 tenure/tenure-track faculty and three research faculty members. “What a journey for the first nuclear engineering curriculum in the nation,” said Kostadin Ivanov, professor and department head.
Alexander M. Parshin
Item ID: 690050|ISBN: 978-0-89448-563-3
1996|1st Edition|359 pages
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Description
An authoritative account by one of Russia's most distinguished metallurgists of the properties and behavior of stainless steels used or proposed for use in nuclear reactors, both fission and fusion. While all of the work reported was carried out on steels with Russian designations, a comprehensive table relates these to U.S. and European designations. The book discusses the environments in which the steels have to perform and at the same time discusses the underlying physical phenomena that control their behavior in service. In addition to steels, there is considerable treatment of titanium and its alloys, which have good resistance to water corrosion and have favorable neutron capture cross sections.
