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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.
Thomas K. Larson, Keith G. Condie, Steven T. Polkinghorne, Brent J. Buescher
Nuclear Technology | Volume 93 | Number 2 | February 1991 | Pages 174-194
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34504
Articles are hosted by Taylor and Francis Online.
An unheated, integral thermal-hydraulic facility scaled to the Advanced Test Reactor (ATR) at the Idaho National Engineering Laboratory was designed, constructed, and operated to gather simulated large-break loss-of-coolant accident (LOCA) data for use in assessing codes used in ATR analysis. Eighteen experiments were performed in the facility to establish a data base consisting of qualitative and quantitative information for assessment purposes. The effects of initial liquid temperature, break location, and use of safety injection are examined. The results obtained offer significant insights about thermal-hydraulic processes in a complex loop during subatmospheric pressure operating conditions similar to those expected during a hypothetical LOCA in the ATR.
