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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.
P.J. Maziasz, A.F. Rowcliffe, M.L. Grossbeck, G.E.C. Bell, E.E. Bloom, D.C. Lousteau, A. Hishinuma, T. Kondo, R.F. Mattas, D.L. Smith
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1571-1579
Material and Tritium | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29565
Articles are hosted by Taylor and Francis Online.
New data on radiation-induced hardening, low-temperature creep and potential susceptibility (sensitization) to aqueous corrosion have been obtained on various heats of austenitic stainless steel (including type 316) irradiated at 60–400°C to 7–13 dpa. The data were obtained from spectral-tailoring reactor experiments, whose radiation-damage parameters are similar to those in the proposed International Thermonuclear Experimental Reactor (ITER) first-wall (FW) and blanket design. Austenitic stainless steels were found to increase significantly in strength at 60–330°C, to have higher irradiation-creep rates at 60°C than at 200–400°C, and to show radiation-induced changes in electrochemical properties at 200–400°C. These data on several radiation-induced property changes suggest that type 316 steel may be an adequate material for the FW of ITER. However, there is definitely a need for new data on fracture-toughness and on fatigue behavior below 400°C, as well as more data on irradiation-creep and effects of irradiation on corrosion properties, to better define temperature and dose dependencies for more detailed design analyses. Cold-working should remain an optional as-fabricated condition for the FW of ITER. Many properties of SA and CW 316 become similar after irradiation at 60–400°C. The higher initial yield-strength of CW 316 will allow higher design stress and elastic strain limits.