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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.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Nuclear Science and Engineering
March 2025
Nuclear Technology
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February 2025
Latest News
Fabrication milestone for INL’s MARVEL microreactor
A team from Idaho National Laboratory and the Department of Energy’s Office of Nuclear Energy (DOE-NE) recently visited Carolina Fabricators Inc. (CFI), in West Columbia, S.C., to launch the fabrication process for the primary coolant system of the MARVEL microreactor. Battelle Energy Alliance (BEA), which manages INL, awarded the CFI contract in January.
Takaharu Fukuzaki, Takashi Kiguchi
Nuclear Technology | Volume 72 | Number 3 | March 1986 | Pages 291-300
Technical Paper | Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Fission Reactor | doi.org/10.13182/NT86-A33767
Articles are hosted by Taylor and Francis Online.
Effective use of the measured readings of sensors in on-line plant monitoring has been studied, based on an error theory. Both the measured reading and the calculated one, obtained by an analytical model of the plant, are treated as observed values, and the maximum-likelihood estimator is determined so as to minimize its mean-squared error. The difference between the estimator and the calculated reading is used to adapt the model to the current plant state and to increase accuracy of the calculated reading. The index of systematicness, which indicates the mutual independence of the two observed values, has been evaluated to determine the step in the procedure where the above adaptation is to be inserted. The error-theory-based model adaptation procedure has been experimentally applied to boiling water reactor power distribution calculations, and its performance has been verified in simulation calculations at different core states and different numbers of in-core neutron monitors by evaluating the expected error of the calculated readings. Compared to the adaptation, which uses the measured readings instead of the estimator, the error is typically lowered by more than 2% and is less affected by the number of monitors.