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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 Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
X-energy receives federal tax credit for TRISO fuel facility
Advanced reactor company X-energy has been awarded $148.5 million in tax credits under the Inflation Reduction Act for construction of its TRISO-X fuel fabrication facility in Oak Ridge, Tenn.
David L. Aumiller, Michael J. Meholic
Nuclear Science and Engineering | Volume 184 | Number 3 | November 2016 | Pages 453-462
Technical Paper | doi.org/10.13182/NSE16-42
Articles are hosted by Taylor and Francis Online.
COBRA-IE is a three-field subchannel analysis code under development at the Bettis Atomic Power Laboratory. The analysis code is being developed as a general-purpose thermal-hydraulic analysis tool with an emphasis on use in an integrated code system for analyzing postulated large-break loss-of-coolant accidents.
The overall accuracy of programs such as COBRA-IE is tied to the ability to predict void fraction. As such, a comprehensive assessment has been made using one-dimensional void fraction data. The results of this assessment are provided in this paper. The assessment utilizes data from nine different experimental facilities. It includes data from air-water and steam-water facilities, heated flow, adiabatic flow, subcooled boiling, saturated boiling, cocurrent upflow, and cocurrent downflow. Approximately 1100 data points are evaluated and included in this assessment. Overall, COBRA-IE was able to predict the void fraction with an average error (predicted − experimental) of less than 0.04. Plots describing the relationship between the error in the prediction and parameters such as pressure and flow are also provided.