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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.
Chang Hyo Kim, Jin Young Cho, Han Gyu Joo
Nuclear Science and Engineering | Volume 118 | Number 2 | October 1994 | Pages 108-121
Technical Paper | doi.org/10.13182/NSE94-A28540
Articles are hosted by Taylor and Francis Online.
Three-dimensional (3D) correction factors designed to take into account the heterogeneity effects of the missing dimension in two-dimensional (2D) reactor computation are rigorously defined. An approximate method for computing the 3D correction factors is proposed by introducing simplified model cores. For verification of the proposed method, 2D and 3D ROCS code computations are performed for the first three cycles of the Yonggwang Unit 2 pressurized water reactor. The utility of the proposed method is then discussed by demonstrating that the 2D ROCS results with the use of the approximate 3D correction factors agree well with the 3D ROCS results in the letdown behavior of the critical soluble boron concentration and the core power distribution.