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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
Standards Program
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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Deep Space: The new frontier of radiation controls
In commercial nuclear power, there has always been a deliberate tension between the regulator and the utility owner. The regulator fundamentally exists to protect the worker, and the utility, to make a profit. It is a win-win balance.
From the U.S. nuclear industry has emerged a brilliantly successful occupational nuclear safety record—largely the result of an ALARA (as low as reasonably achievable) process that has driven exposure rates down to what only a decade ago would have been considered unthinkable. In the U.S. nuclear industry, the system has accomplished an excellent, nearly seamless process that succeeds to the benefit of both employee and utility owner.
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.
