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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.
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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.
César Queral, Antonio Expósito, Alberto Concejal, Pablo Niesutta
Nuclear Technology | Volume 171 | Number 1 | July 2010 | Pages 53-73
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT10-A10772
Articles are hosted by Taylor and Francis Online.
An analysis of the PKL midloop tests E3.1 and F2.2 run 2 was performed with the TRACE (TRAC/RELAP Advanced Computational Engine) and RELAP5/MOD3.3 codes. Both tests allow study of the phenomenology and different accident management actions after a loss of the residual heat removal system at midloop conditions with the primary side closed. A comparison of the results obtained with both codes and the experimental data shows that in general, the main phenomena are well reproduced. The good results obtained allow one to confirm that the modelization methodology is adequate for this kind of transient. However, there are still a few phenomena that are not well predicted, like pressurizer water level behavior.