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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.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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 issues subsequent license renewal to Monticello plant
The Nuclear Regulatory Commission has renewed for a second time the operating license for Unit 1 of Minnesota’s Monticello nuclear power plant.
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.