ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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!
Latest Magazine Issues
Nov 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
NRC okays construction permits for Hermes 2 test facility
The Nuclear Regulatory Commission announced yesterday that it has directed staff to issue construction permits to Kairos Power for the company's proposed Hermes 2 nonpower test reactor facility to be built at the Heritage Center Industrial Park in Oak Ridge, Tenn. The permits authorize Kairos to build a facility with two 35-MWt test reactors that would use molten salt to cool the reactor cores.
Kashuai Du, Po Hu, Lefu Zhang, Weibo Wang
Nuclear Science and Engineering | Volume 193 | Number 10 | October 2019 | Pages 1129-1146
Technical Paper | doi.org/10.1080/00295639.2019.1591094
Articles are hosted by Taylor and Francis Online.
In the passive containment cooling system (PCCS) of an AP1000-type pressurized water reactor nuclear power plant, the air convective heat transfer in the external channel of the containment plays a key role under accident conditions. In this study, the containment external channel is simplified into a large-scale rectangular channel with asymmetric heating, and an experimental and numerical study is conducted to evaluate the air heat transfer characteristics. In addition, the effect of the entry form, which comprises an irregular inlet duct and a pore plate, is considered. First, the results show that heat transfer is enhanced by the entry form, which can be verified by numerical simulation and experiment. Second, when analyzing the air heat transfer characteristics of the actual PCCS annular channel, the Gnielinski correlation is relatively conservative since this correlation hugely underestimates the heat transfer rate of numerical cases in a large-scale rectangular channel with the entry form.