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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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Chicago, IL|Chicago Marriott Downtown
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Latest News
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
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 | 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.