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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
Virtual Meeting
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.
Hirofumi Nakamura, Kanetsugu Isobe, Masaru Nakamichi
Fusion Science and Technology | Volume 54 | Number 2 | August 2008 | Pages 341-345
Technical Paper | Tritium in Fission | dx.doi.org/10.13182/FST08-A1827
Articles are hosted by Taylor and Francis Online.
A research program to control tritium in supercritical CO2 (SC-CO2) gas-cooled reactors is presented. This type of reactor is attractive because it offers higher thermal efficiency and lower reactivity with the primary coolant. This program consists of two activities; development of tritium permeation barriers in the heat exchanger tubes and development of tritium removal method from the SC-CO2. For permeation reduction, a glassy coating was developed as the tritium permeation barrier for the SC-CO2 system. Experimental results showed the physical and chemical integrity of the coating for 100 hours soaking in the SCCO2. Significant permeation reduction of 1/20 to 1/60 are obtained. But, further permeation reduction is desired through a new coating technique development, since the permeation reduction at lower temperatures is small.
