ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
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.”
J. W. Fricano, J. Buongiorno
Nuclear Technology | Volume 184 | Number 1 | October 2013 | Pages 63-77
Technical Paper | Fuel Design/Defects/Examination / Materials for Nuclear Fuels | doi.org/10.13182/NT13-A19869
Articles are hosted by Taylor and Francis Online.
A metal fuel performance code was coupled to a subchannel analysis code to predict, in a computationally efficient way, critical phenomena that could lead to pin failure for steady-state and transient scenarios in sodium-cooled fast reactors. The fuel performance and subchannel codes coupled are FEAST-METAL and an updated version of COBRA-IV-I, respectively. In coupling the codes, the importance of azimuthal temperature and stress effects in the fuel pin were analyzed; it was concluded that azimuthal temperature averaging around the fuel pin is an acceptable approximation. The codes were coupled using a wrapper, the COBRA And FEAST Executer (CAFE), written in the Python programming language. Data from EBR-II was used to confirm and verify CAFE. Finally, CAFE was used to predict the maximum allowable burnup of three different fuel assembly designs (driver fuel, radial blanket, and tight-pitch breed-and-burn fuel) as a function of operating temperature, linear power, fuel composition, cladding thickness, and smear density.