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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.
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Nuclear Science and Engineering
Fusion Science and Technology
NEA issues call to action in report on nuclear cost reductions
A new report from the Paris-based OECD Nuclear Energy Agency declares that nuclear power is needed for countries to meet their Paris Agreement decarbonization and energy security policy goals, but that governmental support for a rapid reduction in the cost of new nuclear capacity through the creation of certain policy frameworks is likely necessary.
B. Zhao, B. H. Mills, S. I. Abdel-Khalik, M. Yoda
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 561-565
Technical Paper | Proceedings of TOFE-2014 | dx.doi.org/10.13182/FST15-122
Articles are hosted by Taylor and Francis Online.
Three-dimensional numerical simulations of a test section modeling a single module of the helium-cooled modular divertor with multiple jets (HEMJ) design were performed to complement experimental studies at nearly prototypical conditions as part of the joint US-Japan effort on plasma-facing components evaluation by tritium plasma, heat, and neutron irradiation experiments (PHENIX). The Spalart-Allmaras turbulence model gave numerical predictions of the cooled surface temperature that were in good agreement with experimental estimates from a new helium loop. The simulations showed that spatial variations in incident heat flux, at least in the form of a Gaussian function, had a negligible effect on cooled surface temperatures.
Our initial results indicate that the numerical predictions of the thermal performance of a single HEMJ module are in reasonable agreement with the experimental studies. The simulations do, however, predict slightly higher heat transfer coefficients (HTCs) than the experimental studies, presumably because they do not account for thermal losses. The HTC appears to be essentially independent of incident heat flux, suggesting that the model can be used to investigate parameters that cannot be determined experimentally in many cases, such as the local HTC and temperature distributions within the divertor pressure boundary, at prototypical conditions.