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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.
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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.”
Meimei Li, James F. Stubbins
Fusion Science and Technology | Volume 44 | Number 1 | July 2003 | Pages 186-190
Technical Paper | Fusion Energy - Fusion Materials | doi.org/10.13182/FST03-A331
Articles are hosted by Taylor and Francis Online.
The influence of radiation damage on the fatigue performance of two selected copper alloys, a dispersion-strengthened CuAl-25 alloy and a precipitation-hardened CuCrZr alloy, was analyzed. The fatigue lives of the two alloys were predicted using their tensile properties before and after irradiation by the Universal Slopes method. The predicted lives are compared with experimental results, and the feasibility of using tensile properties to predict fatigue lives following irradiation is examined. The fatigue performance of these two copper alloys was degraded due to radiation exposure, but the radiation effect on the fatigue performance was not as severe as on the tensile properties. The life prediction agrees reasonably well with the measured fatigue response.