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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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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
Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
Enrico Magnani, Lionel Cachon, Thomas Ihli, Jeremy West
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 935-939
Power Plants, Demo, and Next Steps | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A9030
Articles are hosted by Taylor and Francis Online.
A part of the recent scoping studies for a European DEMO reactor deals with the design of the in-vessel components and their integration inside the reactor. The main in-vessel components are the Breeding Blankets (Helium Cooled Lithium Lead and Helium Cooled Pebble Bed), the helium supply units called Manifolds (MF) and the Neutron Shields. Alternative concepts for the integration of these components have been developed in parallel by different Europe an associations (FZK, CEA, and EFET). Nevertheless these concepts are all based on the vertical segmentation concept called "Multi Module Segment" (MMS). The big advantage of the MMS concept dwells in the fact that blankets and MF constitute a vertical non-permanent segment to be installed and dismantled by Remote Handling (RH) tools through the upper ports of the reactor. The dimensions, geometry and materials are strictly dependent on the harsh conditions of the in-vessel environment: high temperatures, high neutron fluxes, and high thermo-mechanical loads during normal operations and disruptive events. In addition, suitable systems of attachment able to withstand thermal expansion and the expected loads have been developed to provide reliability and easy in-vessel maintenance. The general aspects of the MMS system and the common RH procedures foreseen are presented and the different specific options for solving attachment and in-vessel assembly issues are discussed.