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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Hash Hashemian: Visionary leadership
As Dr. Hashem M. “Hash” Hashemian prepares to step into his term as President of the American Nuclear Society, he is clear that he wants to make the most of this unique moment.
A groundswell in public approval of nuclear is finding a home in growing governmental support that is backed by a tailwind of technological innovation. “Now is a good time to be in nuclear,” Hashemian said, as he explained the criticality of this moment and what he hoped to accomplish as president.
Kenny C. Gross, Keith E. Humenik
Nuclear Technology | Volume 93 | Number 2 | February 1991 | Pages 131-137
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34499
Articles are hosted by Taylor and Francis Online.
It is common practice in nuclear power plants to install redundant sensors to monitor critical physical variables such as pressures, temperatures, and radiation levels. The design and testing of an extremely sensitive component-operability surveillance algorithm based on the sequential probability ratio test (SPRT) are reported. The SPRT technique processes the stochastic components of digitized signals from identical sensors on two or more components in an operating reactor for the detection and annunciation of off-normal operation. Information from the SPRT can provide a reactor operator with early identification of conditions that could lead to plant operational degradation, thus enabling him or her to terminate or avoid events that might challenge safety or radiological performance guidelines. The SPRT enhances plant availability and economics by minimizing unnecessary reactor trips caused in conventional systems by occasional spurious data that might exceed a simple high/low limit check. An example application of the SPRT for the surveillance of primary coolant pump operability in the Experimental Breeder Reactor II is presented.