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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.
Byong-Jo Yun, Dong-Jin Euh, Chul-Hwa Song
Nuclear Technology | Volume 156 | Number 1 | October 2006 | Pages 56-68
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3773
Articles are hosted by Taylor and Francis Online.
Hydraulic phenomena in the downcomer of a conventional pressurized water reactor have an important effect on the transient evaluations of a postulated large-break loss-of-coolant accident (LBLOCA). In particular, safety analyses using best-estimate codes show that downcomer boiling is one of the important phenomena in the postulated LBLOCA because it can degrade the hydraulic head in the downcomer and consequently affect the reflood flow rate for core cooling. To experimentally identify the thermal-hydraulic behavior in the downcomer, a downcomer-boiling test facility was constructed for simulating downcomer boiling in the reflood phase of a postulated LBLOCA.The test facility was designed by adopting a full-pressure, full-height, and full-size downcomer-gap approach but with the circumferential length reduced 47.08-fold. The test was divided into two phases: (a) visual observation and acquisition of the global two-phase flow parameters and (b) measurement of the local two-phase flow parameters.This paper presents the test results from Phase I. The major measured parameters were the axial void fraction and the fluid temperatures and pressures in the test section. The measured data were used to evaluate a safety analysis code, MARS 2.1b, to investigate its modeling accuracy and identify weaknesses of the thermal-hydraulic models therein.