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Division Spotlight
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.
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
Can hydrogen be the transportation fuel in an otherwise nuclear economy?
Let’s face it: The global economy should be powered primarily by nuclear power. And it probably will by the end of this century, with a still-significant assist from renewables and hydro. Once nuclear systems are dominant, the costs come down to where gas is now; and when carbon emissions are reduced to a small portion of their present state, it will become obvious that most other sources are only good in niche settings. I mean, why use small modular reactors to load-follow when they can just produce that power instead of buffering it?
Dawn E. Janney, Steven L. Hayes
Nuclear Technology | Volume 203 | Number 2 | August 2018 | Pages 109-128
Critical Review | doi.org/10.1080/00295450.2018.1435137
Articles are hosted by Taylor and Francis Online.
More than 14 000 U-10Zr fuel rods (alloys of U with 10 wt% Zr) were irradiated in the Experimental Breeder Reactor II and Fast Flux Test Facility, with some irradiated to burnups of almost 20 at. %. However, very little information about properties of unirradiated U-10Zr alloys is available. These data are needed to help with interpretation of data from irradiated materials, to develop and validate phase diagrams and models of U-Zr and more complex systems, to inform and validate fuel performance codes, to design fuels for future fast reactors, and to guide future experimental investigations to fill in crucial gaps in knowledge.
This paper provides a summary and critical review of the available experimental data on phases and phase diagrams, electrical properties, thermal expansion, thermal conductivity, heat capacity, mechanical properties, vapor pressures, and thermodynamic properties of unirradiated U-10Zr alloys. Many of the reported values were published before approximately 1970 and are available only in obscure reports. This critical review concludes by identifying areas where additional experimental measurements are particularly necessary and makes recommendations on prioritization of new measurements with a view to the emerging needs associated with the mechanistic modeling of nuclear fuels and their performance.