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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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.”
Bo-Young Han, Hee-Sung Shin, Ho-Dong Kim
Nuclear Technology | Volume 182 | Number 3 | June 2013 | Pages 369-377
Technical Note | Fuel Cycle and Management | doi.org/10.13182/NT13-A16986
Articles are hosted by Taylor and Francis Online.
Pyrochemical processing (pyroprocessing) was developed to recover plutonium that is inherently comingled with minor actinides, uranium, and fission products and has been studied with the aim of recovering actinide elements from spent nuclear fuel. Although a significant amount of attention has been given to pyroprocessing technology as a future fuel recycling system, safeguards approaches are challengeable because of a lack of international experience with safeguarding pyroprocessing facilities beyond those at a pilot scale. Safeguards have primarily depended on nuclear material accountancy with the measurement uncertainties inherent in nuclear material flow. When the weakness of nuclear material accountancy is addressed, the quantity of material unaccounted for (MUF) is generally regarded as an important measure of the safeguardability of a facility. Statistically, the observed MUF is a random variable that is an estimate of the true MUF because the observed MUF is affected by measurement errors. The MUF uncertainty can be calculated by properly combining the random error and systematic error of the nuclear material accounting measurement. Therefore, in this study, a conceptual design for estimation of the uncertainty of MUF that can occur in a reference pyroprocessing facility (REPF) is developed, where REPF is a model used to optimize the safeguardability of a future pyroprocessing facility.