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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 Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
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.
Srikantam Sravanthi, R. Dheenadhayalan, K. Madhusoodanan, K. Devan
Nuclear Technology | Volume 201 | Number 2 | February 2018 | Pages 180-189
Technical Note | doi.org/10.1080/00295450.2017.1407594
Articles are hosted by Taylor and Francis Online.
Dependability management practices in nuclear power plants in India are conventionally governed by a set of rules known as “safety criteria.” Probabilistic assessments of safety systems are used in a modern plant to complement such rules. In this technical note, various design provisions provided in the instrumentation and control (I&C) of prototype fast breeder reactor (PFBR) (a reactor under commission in India) are detailed. As a precursor, the relationship between safety criteria and the average probability of failure on demand (PFDAvg) of safety systems is established. Subsequently, various design provisions provided in the I&C of PFBR to reduce PFDAvg are discussed. Such a review, with a dependability viewpoint, has resulted in identifying areas for further design improvement in future reactors. Research work carried out in areas of relays toward reducing PFDAvg of safety systems is highlighted.
