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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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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.
Gary L. Solbrekken, Gerhard H. Schnieders, Jerome Rivers (Univ of Missouri, Columbia), Adrian Tentner, Cezary Bojanowski, Erik Wilson (ANL)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 612-624
A series of experimental and numeric studies are being carried out to support the safety assessment of a new potential low-enriched uranium fuel for high power research and test reactors. A set of experiments designed to provide a database of high-fidelity data was obtained on a curved test plate at the University of Missouri flow loop over velocity sweep ranging from a nominal 2 m/s to a nominal 4.3 m/s. The data suggested that there was a hysteresis over the course of the velocity sweeps that could not be explained by pure mechanical arguments. Temperature measurements of the water flowing through the test section indicated that the circulating pump increased the reservoir temperature by about 7 oC over the course of the 120 minute experiment. Numeric simulations of the thermal expansion suggested that plate deflections on the order of 0.025 mm (1 mil), similar to those seen during the flow experiments, were possible at the leading edge of the test plate. Therefore, it is necessary to correct experimental data for thermal expansion if the temperature of water flowing through the test section does increase.