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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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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Nuclear supply chain innovation and collaboration: Keeping the nuclear supply chain viable through change
The next nuclear renaissance may be upon us, but with it comes a perfect storm. The industry is unprepared for a surge in demand for goods and services from both the existing light water fleet and the next generation of reactors. We are currently teetering on the edge of severe supply chain issues, but if the nuclear industry can understand the sources of our challenges, we can mitigate them.
K. Takase, M. Z. Hasan, T. Kunugi
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1840-1844
Plasma-Facing Component | doi.org/10.13182/FST92-A29986
Articles are hosted by Taylor and Francis Online.
Convective heat transfer in non-MHD laminar flow through rectangular channels in the first wall and limiter/divertor plates of fusion reactors has been analyzed numerically. Even for uniform heat flux, the Nusselt number (Nu) is not constant along the face of a rectangular channel, because the velocity is much smaller near a corner. For uniform heat flux, Nu varies by 67% from the center of a side to the corner (6.7 to 2.2). Therefore, the corners of a rectangular channel are possible hot-spot areas of concern for thermal-hydraulic designs. In addition, the surface heat flux on coolant channels in the plasma-facing components varies circumferentially. This nonuniformity of surface heat flux also affects the Nu. At the center of a side, Nu can be reduced from 6.7 to 2.8, i.e. by about 58%. For large nonuniformity of surface heat flux, the Nu at some locations can become infinity or negative; infinity, when the coolant/wall interface temperature becomes equal to the coolant bulk temperature and, negative, when the bulk temperature becomes larger than the interface temperature at these locations. The entry length is also increased due to the nonuniformity of surface heat flux. This increase can be as much as 4 times the entry length for uniform heat flux. For safe thermal-hydraulic designs of the first wall and limiter/divertor plates of fusion reactors, these effects must be taken into consideration.