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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
Tank waste operations resume at Idaho’s IWTU
The Department of Energy’s Office of Environmental Management announced yesterday that waste processing operations have resumed at the Integrated Waste Treatment Unit (IWTU) at the Idaho National Laboratory Site. The resumption of operations follows the completion of two maintenance campaigns at the radioactive liquid waste treatment facility.
Rui Hu, Mujid S. Kazimi
Nuclear Technology | Volume 177 | Number 1 | January 2012 | Pages 8-28
Technical Paper | Fission Reactors | doi.org/10.13182/NT12-A13324
Articles are hosted by Taylor and Francis Online.
The TRACE/PARCS code was applied in this work to examine the validity of the coupled three-dimensional thermal-hydraulics and neutronics system analysis codes for boiling water reactor stability analysis. The evaluation was performed against the Ringhals-1 stability tests and compared with the frequency domain analysis using the code STAB. A comprehensive assessment of modeling choices for the TRACE stability analysis has been made, including effects of time-space discretization and numerical schemes, thermal-hydraulics channel grouping, neutronics modeling, and control system modeling. It was found that with careful control of numerical diffusion, the predictions from TRACE agree reasonably well with the Ringhals-1 test results and the predictions from STAB. The benchmark results of both codes against the Ringhals stability test are found to be at the same level of accuracy. The biases for the predicted global decay ratio are [approximately]0.07 in TRACE results and -0.04 in STAB results. However, the standard deviations of their decay ratios are both large, [approximately]0.1, indicating large uncertainties in both analyses. The uncertainties in both modeling approaches are identified. Although the TRACE code uses more sophisticated neutronics and thermal-hydraulics models, the modeling uncertainty is not less than that of the STAB code.