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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.
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2025 ANS Annual Conference
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Chicago, IL|Chicago Marriott 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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
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.