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Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
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.
Dale L. Smith, Charles C. Baker, Dai Kai Sze, Grover D. Morgan, M. A. Abdou, Steven J. Piet, K. R. Schultz, Ralph W. Moir, James D. Gordon
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 10-44
Overview | Blanket Comparison and Selection Study | doi.org/10.13182/FST85-4
Articles are hosted by Taylor and Francis Online.
The Blanket Comparison and Selection Study (BCSS) was a 2-yr, multilaboratory project initiated by the U.S. Department of Energy/Office of Fusion Energy. Its primary objectives were to (a) define a limited number of blanket concepts that should provide the focus of the blanket research and development (R&D) program, and (b) identify and prioritize critical issues for the leading blanket concepts. The BCSS focused on the mainline approach for fusion reactor development, namely, the D-T-Li fuel cycle, tokamaks and tandem mirror reactors (TMRs) for electrical energy production, and a reactor parameter space that is generally considered achievable with modest extrapolations from the current data base. The STARFIRE and Mirror Advanced Reactor Study reactor and plant designs, with a nominal first-wall neutron load of 5 MW/m2, were used as reference designs for the study. The study focused on