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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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Fusion Science and Technology
Latest News
X-energy receives federal tax credit for TRISO fuel facility
Advanced reactor company X-energy has been awarded $148.5 million in tax credits under the Inflation Reduction Act for construction of its TRISO-X fuel fabrication facility in Oak Ridge, Tenn.
Daniel López, Javier Sanz, Francisco Ogando
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 252-257
IFMIF | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14143
Articles are hosted by Taylor and Francis Online.
During the IFMIF/EVEDA phase, a 125 mA and 9 MeV deuteron prototype accelerator will be designed and tested for the final IFMIF project. Deuteron losses will occur during operation of the accelerator at several components as well as at the beam stopping, leading to material activation induced by deuterons and/or by secondary neutrons, depending on the location. This work is focused on the residual dose rate assessment inside the accelerator vault due to the radioactive inventory induced in the main accelerator components, the outside concrete structures of the accelerator vault, and the concrete-made local shielding of the beam dump. The results will be useful for maintenance work planning, identifying hot areas in the accelerator region. The adopted computational procedure uses MCUNED for determination of spatial distribution of deuteron and neutron fluxes, ACAB for activation calculations, and MCNPX for transport of decay gammas. Deuteron transport cross sections are taken from TENDL-2010 and decay and activation cross-section data from EAF-2007.