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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
The RAIN scale: A good intention that falls short
Radiation protection specialists agree that clear communication of radiation risks remains a vexing challenge that cannot be solved solely by finding new ways to convey technical information.
Earlier this year, an article in Nuclear News described a new radiation risk communication tool, known as the Radiation Index, or, RAIN (“Let it RAIN: A new approach to radiation communication,” NN, Jan. 2025, p. 36). The authors of the article created the RAIN scale to improve radiation risk communication to the general public who are not well-versed in important aspects of radiation exposures, including radiation dose quantities, units, and values; associated health consequences; and the benefits derived from radiation exposures.
P. A. Roth, H. Chow
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 581-585
Blanket and First-Wall Engineering | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40101
Articles are hosted by Taylor and Francis Online.
The ATHENA code is being developed by EG&G Idaho as a general purpose thermal hydraulics code for safety transient analysis of fusion reactors. This report documents the use of ATHENA to model a lithium-lead cooled fusion reactor design. The code models the MHD effects resulting from the flow of a conducting fluid through a strong steady magnetic field. The code performed well within the range of available lithium-lead properties. The results from calculations of several operational transients and a loss of pumping power are reported.
