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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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ANS joins others in seeking to discuss SNF/HLW impasse
The American Nuclear Society joined seven other organizations to send a letter to Energy Secretary Christopher Wright on July 8, asking to meet with him to discuss “the restoration of a highly functioning program to meet DOE’s legal responsibility to manage and dispose of the nation’s commercial and legacy defense spent nuclear fuel (SNF) and high-level radioactive waste (HLW).”
Naomichi Kanegae, Koh Hashiguchi, Ichiro Ikemoto, Masao Hori
Nuclear Technology | Volume 40 | Number 3 | October 1978 | Pages 261-277
Technical Paper | Reactor | doi.org/10.13182/NT78-A26724
Articles are hosted by Taylor and Francis Online.
The wastage effects of a sodium-water reaction resulting from a small leak in a liquid-metal fast breeder reactor steam generator were investigated. These experiments were conducted at low steam injection rates, ranging from 0.07 to 13.8 g/s, with the following test conditions: sodium temperature 480°C, sodium velocity 0.24 m/s, and target material Cr—1 Mo steel. Employed were nozzle diameters (D) from 0.2 to 1.5 mm, nozzle-to-target distances (L) from 5 to 100 mm, and L/D ratios from 7.14 to 400. An empirical equation of wastage rate of Cr— 1 Mo steel was obtained, including parameters of sodium temperature, steam injection rate, and nozzle-to-target distance. The depth curves and the widths of the area affected by wastage were examined. These test results were applied to the safety considerations for the prototype steam generators in Japan.