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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.
M. Araki, M. Ogawa, M. Akiba, S. Suzuki
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1835-1839
Plasma-Facing Component | doi.org/10.13182/FST92-A29985
Articles are hosted by Taylor and Francis Online.
It is one of key issues to predict a critical heat flux (CHF) with the highly subcooled flow boiling and the CHF margin for the promising design of plasma facing components for the next generation fusion machines such as an International Thermonuclear Experimental Reactor and a Fusion Experimental Reactor. In particular, divertor plate is subjected to severe heat loads under a condition for one side heating. Because of no correlations predicting CHF for the highly subcooled flow region with heating on one side of the divertor plate, experimental data which were obtained under one sided heating condition have been evaluated by various existing CHF correlations which are based on a condition for uniform circumferential heating. As results, experimental CHF data of the straight tube are relatively good agreement with some correlations within an accuracy of −20 to +10 %, but no correlations are available in the CHF prediction of the externally-finned tube. Further experiments are necessary to evaluate the applicability of the existing CHF correlations under a condition for one side heating.