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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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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.
D.C. Norris, W. M. Stacey, M. Yaksh, S.M. Ghiaasiaan
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 924-929
Plasma Facing Components Technology (Poster Session) | doi.org/10.13182/FST98-A11963731
Articles are hosted by Taylor and Francis Online.
Heat removal and heat conduction analyses were performed to determine the heat flux limits for a number of possible structural material/coolant combinations: SS316/H2O (5 and 14 MPa), HT-9/H2O (14 MPa), V-4Cr-4Ti/H2O (14 MPa), HT-9/He (15 MPa), and V-4Cr-4Ti/He (15 MPa). A common first-wall design geometry, similar to that of ITER, was used. With H2O coolant and steel, the ASME stress criteria were the most limiting, which constrained the surface heat flux to 0.46 MW/m2 (5 MPa) and 0.41 MW/m2 (14 MPa) for SS316 and to 1.1 MW/m2 for HT-9/H2O (14 MPa). The maximum Be temperature was most limiting for V-4Cr-4Ti/H2O (14 MPa), constraining the heat flux to 1.73 MW/m2. For this first wall geometry, which was optimized for H2O, the He-cooled designs were limited by the 2% pumping power constraint to less than 0.5 MW/m2.
The sensitivity of heat flux limits to maximum allowable material temperatures and to parameters of the model was evaluated.