ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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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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.
A. L. Casadei, P. J. Turinsky
Nuclear Technology | Volume 44 | Number 2 | July 1979 | Pages 221-230
Technical Paper | Reactor | doi.org/10.13182/NT79-A32257
Articles are hosted by Taylor and Francis Online.
Accurate and economical methods have been developed to model water density feedback in diffusion calculations for application to pressurized water reactors. Spectral variations of the two-group macroscopic cross sections are accurately modeled by second-order polynomials in water density. Open channel and subcooled boiling effects on the core’s water density distribution are evaluated by coupling three-dimensional thermal-hydraulic and neutron diffusion computer codes. The costly requirement of numerical mesh compatibility between these codes is removed without loss of accuracy. The margin to fuel degradation limits during accident conditions is found to increase when the improved feedback model is employed, serving as a stimulus for further usage.