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Division Spotlight
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.
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.”
Efstathios Vlassopoulos (EPFL), Ramil Nasyrow, Dimitrios Papaioannou, Vincenzo V. Rondinella (EC-JRC), Stefano Caruso (Nagra), Andreas Pautz (EPFL/Scherrer Inst)
Proceedings | 16th International High-Level Radioactive Waste Management Conference (IHLRWM 2017) | Charlotte, NC, April 9-13, 2017 | Pages 726-733
The investigation of the mechanical integrity of spent nuclear fuel rods in accidental scenarios is the main objective of this research, conducted at the hot-cell facilities of the Joint Research Centre (JRC) - Karlsruhe. Two devices for mechanical testing on fuelled, pressurized spent nuclear fuel rod segments have been developed for gravitational impact and 3-point bending tests. The main objectives of this program are the determination of rod response to external load, rod failure conditions and the characterization of fuel release in case of rod fracture. The campaign consists of two phases, namely the development and optimization of the testing devices in "cold" laboratories and their installation and application to test irradiated spent fuel in hot-cells. This paper focuses on the main stages of the development and optimization of the new devices, detailing the motivation behind them and their extended data acquisition capabilities. Representative results on the response of SNF to these dynamic and quasi static loads are presented. The load-deflection curves for the fuel/cladding ensemble and the characterization (mass/size distribution) of released fuel debris following SNF fracture are described.