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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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 updating GEIS rule for new nuclear technology
The Nuclear Regulatory Agency is issuing a proposed generic environmental impact statement (GEIS) for use in reviewing applications for new nuclear reactors.
In an April 17 memo, NRC secretary Carrie Safford wrote that the commission approved NRC staff’s recommendation to publish in the Federal Register a proposed rule amending 10 CFR Part 51, “Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions.”
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.
