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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Igor Salamun, Andrej Stritar
Nuclear Technology | Volume 124 | Number 2 | November 1998 | Pages 118-137
Technical Paper | Reactor Operations and Control | doi.org/10.13182/NT98-A2913
Articles are hosted by Taylor and Francis Online.
Diagnostic methodologies for nuclear power plants (NPPs) are usually based on mathematical models and generation of residuals. To avoid complicated, time-consuming, and costly diagnostic simulations of the physical phenomena in NPPs, an algorithm that determines a significant pattern for major transients is investigated. Coefficients of the transfer function between the observed parameters are used as the pattern features. The algorithm uses a recurring least-squares method known from the literature to determine the transfer functions. The case study includes 30 different scenarios in the primary and secondary systems. Each scenario produces its own significant recognized pattern. The RELAP5/MOD3.2 code is used to simulate the input data for the Krsko pressurized water reactor NPP. The algorithm recognizes the prepared scenarios, and it classifies them into groups.