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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Latest News
Recent surveys confirm high levels of U.S. nuclear support
Surveys have consistently indicated that public support in the United States for the use of nuclear energy has been increasing in recent years. Four recent surveys continue to suggest that near-record-high numbers of Americans support nuclear energy. However, the survey results differ—sometimes widely—in the details of their findings.
C. P. C. Wong et al.
Fusion Science and Technology | Volume 64 | Number 3 | September 2013 | Pages 623-630
Test Blanket, Fuel Cycle, and Breeding | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 2) Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST13-A19161
Articles are hosted by Taylor and Francis Online.
Under the US Fusion Nuclear Science and Technology Development program, we have selected the Dual Coolant Lead Lithium concept (DCLL) as a reference blanket, which has the potential to be a high performance DEMO blanket design with a projected thermal efficiency of >40%. Reduced activation ferritic/martensitic (RAF/M) steel is used as the structural material. The self-cooled breeder PbLi is circulated for power conversion and for tritium breeding. A SiC-based flow channel insert (FCI) is used as a means for magnetohydrodynamic pressure drop reduction from the circulating liquid PbLi and as a thermal insulator to separate the high-temperature PbLi (~700°C) from the helium-cooled RAF/M steel structure. We are making progress on related R&D needs to address critical Fusion Nuclear Science and Facility (FNSF) and DEMO blanket development issues. While performing the function as the Interface Coordinator for the DCLL blanket concept, we were developing the mechanical design and performing neutronics, structural and thermal hydraulics analyses of the DCLL TBM module. We estimated the necessary ancillary equipment that will be needed at the ITER site, and a detailed safety impact report was prepared. This provided additional understanding of the DCLL blanket concept in preparation for the FNSF and DEMO. This paper is a summary report on the progress of the DCLL TBM design and R&D for the DCLL blanket concept.