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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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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
B. H. Mills, J. D. Rader, D. L. Sadowski, M. Yoda, S. I. Abdel-Khalik
Fusion Science and Technology | Volume 64 | Number 3 | September 2013 | Pages 670-674
Test Blanket, Fuel Cycle, and Breeding | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 2) Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST12-527
Articles are hosted by Taylor and Francis Online.
As part of the ARIES study, the Georgia Tech group has experimentally studied the thermal performance of a helium-cooled `finger-type' tungsten divertor design that uses jet impingement and a fin array to cool the plasma-facing surface. These studies were performed using air at Reynolds numbers Re, spanning those for prototypical operating conditions. A brass test section heated with an oxy-acetylene torch at incident heat fluxes up to 2 MW/m2 was used. Recently, data obtained with room-temperature helium suggests that dynamic similarity between the air and helium experiments cannot be achieved by only matching Re because of the difference in the relative contributions of convection and conduction through the annular side walls of the divertor. Numerical simulations suggest that achieving dynamic similarity requires matching the ratio of the thermal conductivity of the divertor module material to that of the coolant under operating conditions, as well as Re.Studies were performed to verify that experiments at the prototypical Re and thermal conductivity ratio using helium at room temperature give Nusselt numbers Nu that are dynamically similar to those at prototypical operating conditions. Given that the thermal conductivity of helium decreases as temperature decreases, matching of the thermal conductivity ratio required a carbon steel test section with a thermal conductivity much lower than that of the brass alloy previously used. The resulting ratio of the test section to coolant thermal conductivities is similar to that of the tungsten alloy and helium at prototypical conditions. The data were used to verify generalized correlations for Nu, as a function of Re and the thermal conductivity ratio. The correlations can be used to determine the maximum heat flux that can be accommodated by the divertor at prototypical conditions.