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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 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.
M. C. Chuang, M. D. Carelli, C. W. Bach, J. S. Killimayer
Nuclear Science and Engineering | Volume 64 | Number 1 | September 1977 | Pages 244-257
Technical Paper | doi.org/10.13182/NSE77-A27095
Articles are hosted by Taylor and Francis Online.
A study is presented to determine the detailed coolant velocity and temperature profile around the entire rod circumference in liquid-metal fast breeder reactor (LMFBR) core assemblies as well as the detailed radial and circumferential temperature profile in the rod. The digital computer code FATHM-360 developed to perform the above calculations is described. Fuel, radial blanket, and control assembly rods (both wire-wrapped and bare) can be analyzed. Coolant, cladding, and fuel (or absorber) temperature profiles are calculated for uniform and nonuniform heat generation (i.e., accounting for power skew across the pellet) in the rod. Temperature distributions can be calculated for both concentric and eccentric positions of the pellet with respect to the fuel rod cladding. Typical examples of the calculational capabilities of the code are presented. Such capabilities are needed for a reliable design of LMFBR core assemblies and rods to provide detailed cladding temperature profiles and accurately calculate the cladding strain on which the fuel rod lifetime and allowable burnup depend. Overall, a more realistic core thermofluids design is possible by implementing the study presented here.