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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
Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
Naoyuki Kisohara, Takeshi Moribe, Takaaki Sakai
Nuclear Technology | Volume 164 | Number 1 | October 2008 | Pages 103-118
Technical Paper | Icapp '06 | doi.org/10.13182/NT08-A4012
Articles are hosted by Taylor and Francis Online.
A sodium-heated steam generator (SG) being studied in Japan for a future commercialized fast reactor is a double-wall straight tube type. The SG is large to reduce its manufacturing cost by economies of scale. This paper addresses the multidimensional distributions of the temperature and the flow in the SG. Large heat exchanger components are prone to have nonuniform flow and temperature distributions. These maldistributions cause tubes to have thermal expansion mismatch, which might lead to structural issues such as tube buckling or tube-to-tube-sheet junction failure in straight tube SGs. The temperature profiles in the SG are examined by numerical methods, and flow distribution control devices are optimized to prevent these issues. The calculation model of the SG consists of two parts: a sodium inlet distribution plenum (the inlet plenum) and a heat transfer tube bundle region (the bundle). The flow and temperature distributions in the inlet plenum and the bundle are evaluated by the three-dimensional code FLUENT and the two-dimensional code MSG, respectively. The thermal loads on the tubes are evaluated by the structural code FINAS based on the temperature distributions. These codes have revealed that the sodium flow is distributed uniformly by the flow distributors and that the thermal loads remain within the allowable range for the structural integrity of the tubes and the junctions. An inlet plenum water test and an SG experiment to examine thermal-hydraulic performance are planned. These tests will reveal the flow and temperature distributions in the SG and verify the computer calculation results.