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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
NRC wants input on Hermes 2 test reactor construction permit
The Nuclear Regulatory Commission is seeking input on its draft environmental assessment and draft finding of no significant impact for Kairos Power’s application to build the Hermes 2 test reactor facility in Oak Ridge, Tenn.
H. Madarameb, K. Taghavi, M.S. Tillack
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 264-269
Blanket and First-Wall Engineering | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40055
Articles are hosted by Taylor and Francis Online.
The MHD pressure drop in the second wall orifice which connects the first wall cooling channel and the header in one of the BCSS blankets is discussed. Though the second wall is thin, the pressure drop in the orifice can be very large because of leakage current effects. If eddy currents leak and do not have to pass through thin walls, the resistivity of the current path may be low and the current intensity may be high, which induces a high pressure drop. The presence of leakage current greatly affects the MHD pressure drop in fusion reactor blankets.