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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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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What’s the most difficult question you’ve been asked as a maintenance instructor?
Blye Widmar
"Where are the prints?!"
This was the final question in an onslaught of verbal feedback, comments, and critiques I received from my students back in 2019. I had two years of instructor experience and was teaching a class that had been meticulously rehearsed in preparation for an accreditation visit. I knew the training material well and transferred that knowledge effectively enough for all the students to pass the class. As we wrapped up, I asked the students how they felt about my first big system-level class, and they did not hold back.
“Why was the exam from memory when we don’t work from memory in the plant?” “Why didn’t we refer to the vendor documents?” “Why didn’t we practice more on the mock-up?” And so on.
Yongwei Chen, Zeyong Zhang, Dong Li
Nuclear Technology | Volume 204 | Number 3 | December 2018 | Pages 378-385
Technical Paper | doi.org/10.1080/00295450.2018.1477394
Articles are hosted by Taylor and Francis Online.
To effectively reduce the probability of instrumentation and control (I&C) equipment aging failures in nuclear power plants, a preventive replacement aging treatment strategy should be adopted. A single failure–oriented and component aging sensitivity classification model is put forward to classify I&C equipment aging in nuclear power plants, and three methods for assessing I&C equipment life cycles (i.e., aging tests, standards and specifications, and failure data) are provided. Meanwhile, provided with the characteristic curves of I&C equipment aging failures in nuclear power plants, specific aging treatment steps are put forward, including (1) defining the scope of aging treatment in horizontal and longitudinal dimensions of signal flow direction and equipment composition; (2) determining the aging treatment implementation cycle by a life cycle margin setting method; (3) refining the aging treatment implementation process by division of four stages, namely, aged equipment classification, aging data management, aging treatment implementation, and aging testing feedback, to ensure reliable and safe operation of I&C equipment in nuclear power plants.