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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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Empowering the next generation: ANS’s newest book focuses on careers in nuclear energy
A new career guide for the nuclear energy industry is now available: The Nuclear Empowered Workforce by Earnestine Johnson. Drawing on more than 30 years of experience across 16 nuclear facilities, Johnson offers a practical, insightful look into some of the many career paths available in commercial nuclear power. To mark the release, Johnson sat down with Nuclear News for a wide-ranging conversation about her career, her motivation for writing the book, and her advice for the next generation of nuclear professionals.
When Johnson began her career at engineering services company Stone & Webster, she entered a field still reeling from the effects of the Three Mile Island incident in 1979, nearly 15 years earlier. Her hiring cohort was the first group of new engineering graduates the company had brought on since TMI, a reflection of the industry-wide pause in nuclear construction. Her first long-term assignment—at the Millstone site in Waterford, Conn., helping resolve design issues stemming from TMI—marked the beginning of a long and varied career that spanned positions across the country.
T. Shimooke
Nuclear Technology | Volume 10 | Number 3 | March 1971 | Pages 257-272
Technical Paper | Reactor | doi.org/10.13182/NT71-A30958
Articles are hosted by Taylor and Francis Online.
Various core performances, such as power and void distributions in a core, reactivity change, and shifts of control rods, are predicted for the JPDR-1 in a three-dimensional framework by means of the one-energy-group coarse-mesh approximation of the boiling water reactor (BWR) core. The predictions are checked in detail with experimental data that were accumulated by “the core-performance assessment experiments” done throughout the life of the JPDR-1 core. The data include y-probing data of the core at the exposure of each 1000 MWd/ton (approximately) core outlet void fractions measured directly by voidmeters, logbook records of the control rod patterns, heat-balance data for the precise core outputs, and others. In conclusion, the one-energy-group coarse-mesh approximation of the BWR is proved to be satisfactory for describing the global core performances of the JPDR-1 for burnup cases. The global power distributions can be calculated, e.g., with 4% standard deviation in the channel power sharing, and this is accurate enough to predict the core reactivity within 0.3% Δk/k error at 6000-MWd/ton exposure. The observed discrepancy, 0.9% Δk/k in the core reactivity at 6000-MWd/ton exposure (i.e., 10 to 15% error of the burnup change of reactivity), is discussed, with the final suggestion that the local power and exposure distribution in a core should be studied first, among others, for better achievement of the global core description.