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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.
Aya Diab, Michael Corradini, Carl Martin
Nuclear Technology | Volume 169 | Number 2 | February 2010 | Pages 114-125
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT10-A9356
Articles are hosted by Taylor and Francis Online.
Pressurized heavy water reactors of the CANDU design may be susceptible to a partial or a complete blockage of the flow of coolant to some of the pressure tubes. This event, although very rare, would result from the presence of debris in the heat transport conduits. In the case of an extreme event where the coolant flow is blocked completely, in addition to failure to scram the reactor, an accident scenario may prevail. Coolant trapped in the pressure tube is expected to boil off; the fuel rods would overheat and partially melt with the melt accumulating at the bottom of the pressure tube. This degraded situation, along with the high pressure involved under normal operation conditions, would lead to a rupture of the pressure tube. The pressure signature at the rupture site predicted from a lumped parameter phenomenological model is used as an input to a three-dimensional ANSYS model to assess the pressure signature at the inner walls of the tank in response to the pressure tube rupture. The pressure predicted by the ANSYS model is benchmarked against experimental data from the literature.