ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
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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Nuclear Technology
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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.
L. E. Hansen, E. D. Clayton
Nuclear Technology | Volume 6 | Number 4 | April 1969 | Pages 381-390
Technical Papers and Note | doi.org/10.13182/NT69-A28348
Articles are hosted by Taylor and Francis Online.
Lack of experimental data for nuclear criticality control over operations with plutonium necessitates the use of computed critical parameters for guidance. To provide guidelines for criticality safety use, survey calculations for unreflected and water-reflected spheres, semi-infinite cylinders, and semi-infinite slabs have been made, using calculational techniques confirmed by available experimental data. The Pu(metal)-water mixtures examined cover the entire range of possible moderation ratios and have isotopic 240Pu contents of 20%. Critical experiment data for water-reflected spherical systems containing Pu(NO3)4 solutions with 435g Pu/liter at 4.6 wt% 240Pu were extrapolated by means of calculations to 239Pu(metal)-water mixtures for a direct comparison between calculations and experimentally derived critical parameters. The effect of 240Pu on criticality was examined as a function of both concentration and geometry. The manner in which 240Pu affected the minimum critical mass of Pu(metal)-water systems was also determined.