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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
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.