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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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2021 Student Conference
April 8–10, 2021
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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
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.
A. N. Perevezentsev, A. C. Bell, L. A. Rivkis, V. M. Filin, V. V. Gushin, M. I. Belyakov, V. I. Bulkin, I. G. Prykina, I. M. Kravchenko, A. A. Semenov, A. I. Davidov, S. P. Eliseev, D. V. Titov
Fusion Science and Technology | Volume 52 | Number 1 | July 2007 | Pages 84-99
Technical Paper | dx.doi.org/10.13182/FST07-16
Articles are hosted by Taylor and Francis Online.
Several methods of decontamination, such as melting, heating with flame, isotopic exchange with gaseous hydrogen, replacement with hydrogen, and thermal desorption under moist gas, were tested on stainless steel, INCONEL®, beryllium, copper, and aluminum bronze contaminated with tritium. The detritiation methods were assessed with respect to the fraction of the tritium inventory removed, the residual tritium concentration remaining, and the reduction in the rate of tritium outgassing. Potential applications of these decontamination methods include detritiation of the Joint European Torus (JET) vacuum vessel and the tritium plant prior to dismantling for decommissioning and subsequent processing of the intermediate-level waste this has generated.
