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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.
S.D. Harkness, J. A. Tesk, Che-Yu Li
Nuclear Technology | Volume 9 | Number 1 | July 1970 | Pages 24-30
Fuel Cladding Model | Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material | doi.org/10.13182/NT70-A28724
Articles are hosted by Taylor and Francis Online.
A model has been developed for the evolution of voids and dislocation loops during fast neutron irradiation of austenitic stainless steel. The model is based on a thermodynamic approach that calculates void nucleation and growth rates in terms of the supersaturation of vacancies and interstitials. It is recognized that the steady-state point-defect concentrations decrease with fluence as the result of the creation of additional sinks (voids and loops). The ability to monitor both the microstructural development and the steady-state concentrations of defects allows discussion of the in-pile mechanical properties. The yield strength of austenitic stainless steel is expected to increase rapidly during irradiation at 400°C due to the effectiveness of voids and dislocation loops as obstacles to dislocation motion. Irradiation at 600°C is predicted to result in a slowly increasing yield strength. In-reactor creep behavior is discussed in terms of a climb-controlled model for a dispersion strengthened system. Radiation-enhanced climb is expected to predominate at lower temperatures and stresses over the thermal climb component. Discussion of the possible effects of neutron flux and fluence on the in-pile steady-state creep rate is also included.