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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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U.S. nuclear capacity factors: Ideal for data centers?
Baseload nuclear generation doesn’t get the respect it deserves, if you ask nuclear operators. But the hyperscale data centers that process our digital lives—like the one right next to the Susquehanna plant in northeastern Pennsylvania—are pushing electricity demand up. Clean, reliable capacity now looks a lot more valuable.
W. S. Yeung, Jen Wu, R. T. Fernandez, R. K. Sundaram
Nuclear Technology | Volume 101 | Number 2 | February 1993 | Pages 244-251
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT93-A34786
Articles are hosted by Taylor and Francis Online.
The results of the transient behavior of the water cannon phenomenon determined by RELAP5/MOD3 Version 5m5 are presented. The physical system consists of a 0.7112-m-long, 0.0381-m-i.d. vertical tube partially immersed in a reservoir of subcooled water. The tube is closed at the top and initially filled with saturated steam. The water cannon is created when a liquid slug is drawn into the tube because of the rapid condensation of the steam. In a fraction of a second, the liquid slug strikes the top end of the tube and causes a large pressure spike. The primary objective is to apply the RELAP5/MOD3 computer code to analyze the water cannon event and assess the ability of RELAP5/MOD3 to simulate fast two-phase transients. The sensitivity of time-step size and mesh size has been studied. It is found that RELAP5/MOD3 adequately simulated the transient process with a mesh size of 0.07112 m (i.e., ten nodes) and a time-step size of 10−5 s. The calculated peak pressure of the first pressure spike is of the same order of magnitude as experimental data from literature. The effect of reservoir temperature on the magnitude of the first pressure spike is also studied, and it is found that the pressure peak value decreased with increasing reservoir temperature.