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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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.
Won-Pil Baek, Chul-Hwa Song, Byong-Jo Yun, Tae-Soon Kwon, Sang-Ki Moon, Sung-Jae Lee
Nuclear Technology | Volume 152 | Number 2 | November 2005 | Pages 183-195
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT05-A3669
Articles are hosted by Taylor and Francis Online.
The thermal-hydraulic integral effect test (IET) program is being progressed by the Korea Atomic Energy Research Institute. This paper presents an overview of the IET program; the scientific design characteristics of the IET facility; ATLAS, which is under construction; and the experimental and analytical validation works. The ATLAS facility has the following characteristics: (a) a 1/2-height, 1/288-volume, full-pressure simulation of the APR1400, (b) geometrical similarity with the APR1400, including 2 (hot legs) × 4 (cold legs) reactor coolant loops, a direct vessel injection (DVI), an integrated annular downcomer, etc., (c) incorporation of the specific design characteristics of the 1000-MW(electric) class Korean Standard Nuclear Power Plant, such as a cold-leg injection and the low-pressure injection pumps, (d) a maximum 8% of the scaled nominal core power, and (e) simulation capability of broad scenarios, including the reflood phase of the large-break loss-of-coolant accidents (LOCAs), small-break LOCA scenarios including the DVI line breaks, steam generator tube ruptures, main steam line breaks, midloop operation, etc. The scientific design of the ATLAS was accomplished rigorously from the viewpoints of both a global and local scaling based on the three-level scaling methodology of Ishii et al. The validation works showed that the scientific design of the ATLAS test facility is sound.