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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
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.