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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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
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?
Fabrice Bentivoglio, Nicolas Tauveron
Nuclear Technology | Volume 164 | Number 1 | October 2008 | Pages 55-75
Technical Paper | Icapp '06 | doi.org/10.13182/NT08-A4008
Articles are hosted by Taylor and Francis Online.
In the framework of Generation IV, the Commissariat à l'Energie Atomique studies different concepts of gas-cooled reactors (GCRs). The estimation of thermal-hydraulic performances in steady-state and in transient operations is of high importance for the designer of such systems. These evaluations require efficient and reliable simulation tools capable of modeling the whole reactor, including the core, the core vessel, the piping, the heat exchangers, and the turbomachinery. CATHARE2 is a thermal-hydraulic one-dimensional reference safety code developed and assessed for pressurized water reactors. It has been adapted to deal also with GCR applications. The assessment for these new applications requires cross comparisons with experimental representative data. Thus, CATHARE2 is validated against existing experimental data, in particular, the German power plant Oberhausen II data. Oberhausen II was a 50-MW(electric) direct-cycle helium turbine plant, operated by the German utility Energie Versorgung Oberhausen. This paper presents the plant, with a large emphasis on the helium power conversion unit, the modeling, and the comparison between experimental data and simulation results for both steady-state and transient cases. The agreement between the experimental data and the CATHARE results is quite satisfactory for the analyzed cases.