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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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Latest News
NRC begins special inspection at Hope Creek
The Nuclear Regulatory Commission is conducting a special inspection at Hope Creek nuclear plant in New Jersey to investigate the cause of repeated inoperability of one of the plant’s emergency diesel generators, the agency announced in a February 25 news release.
Hidemasa Kato, Tohru Haga, Shigeru Ohteru, Hiroshi Kamikawa
Nuclear Science and Engineering | Volume 87 | Number 4 | August 1984 | Pages 361-380
Technical Paper | doi.org/10.13182/NSE84-A18505
Articles are hosted by Taylor and Francis Online.
A core management analysis of a 165-MW(electric) plutonium-uranium mixed-oxide-fueled heavy water reactor, Fugen, has been carried out and compared with some of the operational data through the initial cycle and three reload cycles. During these burnup cycles, the Fugen reactor has experienced refueling of 72 plutonium-uranium fuel bundles and 76 UO2 fuel bundles, including four special bundles for irradiating test samples. The core burnup, thermal flux distribution, power distribution, coolant flow distribution, etc., were calculated and compared with measurements. The root-mean-square (rms) error of the calculated thermal flux over the three-dimensional spatial nodes was found to be ∼3% for various core conditions, and the rms error of the calculated core flow distribution was within 2%. The reload patterns have been chosen in such a way that mixed oxide and UO2 fuel bundles can exist in a mixed bed loading with no attendant reactor control problems.