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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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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.
T. Muroga, T. Tanaka, M. Kondo, T. Nagasaka, Q. Xu
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 897-901
Test Blanket Modules | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | dx.doi.org/10.13182/FST09-A9024
Articles are hosted by Taylor and Francis Online.
Combination of liquid lithium with Reduced Activation Feritic/Martensitic Steel (RAFM) is one of the options for Test Blanket Module (TBM) in early ITER period and early DEMO blanket, as well as an intermediate step toward Li/V DEMO blanket. In this paper, characterization of a Li/RAFM blanket was carried out and compared with a Li/V blanket from neutronics and compatibility viewpoints.Although the local Tritium Breeding Ratio (TBR) will be reduced by ∼0.1 by the change from Li/V to Li/RAFM, Li/RAFM seems to be still feasible, with enhanced neutron shield, from the tritium self-sufficiency viewpoint. A similar tritium production rate for the Li/V and the Li/RAFM TBMs suggests that the Li/RAFM TBM simulates well the tritium production of Li/V TBM and thus will be suitable for Li/V DEMO blanket design as well as Li/RAFM blanket.Based on the available data, V-alloys are thought to be highly compatible with Li when the impurity level in the Li is low. New compatibility experiments of RAFM with Li showed transformation of martensitic to ferritic phase in addition to corrosion loss. However, the compatibility issue is estimated to be small for ITER-TBM conditions.The present study showed the significance of starting with a Li/RAFM TBM during the early phase of ITER operation for development of both Li/RAFM and Li/V DEMO blankets.
