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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Former NRC commissioners lend support to efforts to eliminate mandatory hearings
A group of nine former nuclear regulatory commissioners sent a letter Wednesday to the current Nuclear Regulatory Commission members lending support to efforts to get rid of mandatory hearings in the licensing process, which should speed up the process by three to six months and save millions of dollars.
Y. J. Chung, S. H. Yang, H. K. Kim, M. K. Chung, K. K. Kim
Nuclear Technology | Volume 165 | Number 1 | January 2009 | Pages 32-42
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT09-A4060
Articles are hosted by Taylor and Francis Online.
An experiment on a heat transfer and a natural-circulation performance for an integral-type reactor have been carried out using the VISTA facility, and the calculated results using the TASS/SMR and MARS codes have been compared with the experimental results. The VISTA is an experimental facility that consists of a primary system, a secondary system, and a passive residual heat removal system (PRHRS), to simulate the SMART (SysteM integrated modular Advanced ReacTor) plant. The experimental results show that the fluid is stabilized well in the primary system and the PRHRS under natural-circulation conditions. The TASS/SMR and MARS codes predict the overall characteristics of the natural circulation in the primary system and the PRHRS well. From the calculation results, most of the heat transferred from the primary system is removed at the PRHRS heat exchanger by a condensation heat transfer. Under natural-circulation conditions in the integral reactor, a smoothing function at the transition region between different heat transfer modes will be adopted in the TASS/SMR code and a pressure-loss model needs to be improved on the cross-flow bundle geometry in the MARS code.