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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.
Govinda S. Srikantiah
Nuclear Technology | Volume 100 | Number 2 | November 1992 | Pages 216-227
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34744
Articles are hosted by Taylor and Francis Online.
The development, validation, and applications of the VIPRE code are presented. The development of specifications for a reactor core subchannel thermal-hydraulics analysis code for utility applications in the evaluation of reactor safety limits during normal operation and accident scenarios is traced. The capabilities of the VIPRE-01 code based on a homogeneous equilibrium model of two-phase flow with algebraic slip are presented along with a discussion of the extensive verification and validation of the code. Utility applications of the code, which received a safety evaluation report from the U.S. Nuclear Regulatory Commission in 1986, in the areas of fuel reload safety analysis, critical heat flux correlation development and testing, thermal margin analysis, and core thermal-hydraulic analysis are presented. The functional specifications and the development of VIPRE-02, an advanced version of the code based on a two-fluid model of two-phase flow that is capable of simulating the reactor core, vessel, and internal structure, are also described. A discussion of the developing applications for VIPRE-02, such as boiling water reactor instability analysis and pressurized water reactor steamline break analysis, is given with some initial results.