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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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.”
Sei-Hun Yun et al.
Fusion Science and Technology | Volume 60 | Number 1 | July 2011 | Pages 373-378
Materials Development & Plasma-Material Interactions | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 1) | doi.org/10.13182/FST11-A12383
Articles are hosted by Taylor and Francis Online.
Experiments were conducted to obtain thermo physical properties of ZrCo and ZrCo hydride, which determine heat transfer phenomena in the hydrogen-ZrCo system. Heat capacity, thermal diffusivity and thermal conductivity of ZrCo and ZrCo hydride using Baotou ZrCo (China) are found to have U shaped curvatures with the temperature increase. In the temperature range of 300 - 500 K the thermal conductivity of ZrCoHx was found to be about 2/3 that of ZrCo and the initial hydrogen content of ZrCoHx used in this study was taken to be x=2.0.