ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.
Keith Humenik, Kenny C. Gross
Nuclear Science and Engineering | Volume 112 | Number 2 | October 1992 | Pages 127-135
Technical Paper | doi.org/10.13182/NSE92-A28409
Articles are hosted by Taylor and Francis Online.
Sequential probability ratio tests (SPRTs) are applied to the monitoring of nuclear power reactor signals. The theory of SPRTs applied to correlated data that have an unknown distribution is very incomplete. Unfortunately, a common problem regrading the application of sequential methods to reactor variables is that the variables are often contaminated with noise that is either non-Gaussian or serially correlated (or both). A Fourier series approximation can be used to remove much of the correlation in the data. This method is relatively simple to implement but has the desirable property of reducing correlation, thereby allowing the assumption of Gaussian, independent data to hold more readily. Delayed neutron signal data and reactor coolant pump data are analyzed. The theory has been validated by extensive testing with data from the Experimental Breeder Reactor II. The use of SPRT techniques as decision aids in two artificial intelligence-based expert systems for surveillance and diagnosis applications in nuclear reactors is also discussed.