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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.
Hsiang-Shou Cheng, David J. Diamond, Ming-Shih Lu
Nuclear Technology | Volume 37 | Number 3 | March 1978 | Pages 246-260
Technical paper | Reactor | doi.org/10.13182/NT78-A31993
Articles are hosted by Taylor and Francis Online.
An extensive study of boiling water reactor scram reactivity behavior is presented. It is based on a spacetime analysis using a two-dimensional (R,Z) dynamics code that includes a two-phase thermal-hydraulics model. Calculations were made of the sensitivity of scram to such physical quantities as initial control rod position and power distribution, scram speed, system pressure, and varying inlet flow rate and temperature. The end-of-cycle Haling operating condition with all rods initially withdrawn was found to give rise to the limiting scram reactivity function. Calculations were also made to find the effect on scram of commonly used modeling approximations. These included the effect of neglecting delayed neutrons (conservative), using a time invariant void distribution (nonconservative), and defining point kinetics parameters in terms of different weighting functions. The importance of defining these parameters consistent with their use in plant transient analyses was also demonstrated.