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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.
Utility Working Conference and Vendor Technology Expo
August 8–11, 2021
Marco Island, FL|JW Marriott Marco Island
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Nuclear Science and Engineering
Fusion Science and Technology
New polls show substantial support for nuclear energy
Sixty percent of respondents in a recent national survey favored the use of nuclear energy, with only 25 percent opposing its use. While the latest Bisconti Research poll focuses on nuclear power and electricity generation, its findings on public interest in climate change and using a spectrum of sources to meet energy needs are consistent with a recent Pew Research Center poll on a broad set of energy policy and climate change topics. The approaches the two online surveys took to measuring public opinion on nuclear energy yielded different numbers but found some common ground.
S. Domingo, Y. Herreras, F. Sordo, A. Lafuente, J. M. Perlado
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 710-717
Nuclear Analysis | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | dx.doi.org/10.13182/FST09-A8992
Articles are hosted by Taylor and Francis Online.
This paper presents a methodology for 3D neutronic calculations suitable for complex and extensive geometries. The geometry of the system design is first fully modeled with a CAD program; this modeling is then processed - requiring few simplifications - with MCNP-CAD interface in order to generate a MCNP geometry file. Neutronic irradiation results are finally achieved running the MCNP program, where the geometry input card used is directly the MCNP-CAD interface output. This methodology enables accurate neutronic calculations for complex geometries characterized by high detail levels, such as ITER or other fusion facilities (IFMIF), in which we are presently involved.This procedure has been applied to the Fast Ignition Fusion Reactor KOYO-F. We have determined the neutron fluxes and energy deposition in the reactor blanket, and obtained the front panel damage and activation for several alternative front panel materials. To carry out this calculation, KOYO-F blanket design is modeled using CATIA V5, and the selected CAD-MCNP interface is MCAM, developed by the FDS Team (China). The activation of the front panel material is finally evaluated with our code ACAB, based on the neutronic irradiation results provided by MCNP.