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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.
Min-Ho Baek, Sang-Ji Kim, Jaewoon Yoo, In-Ho Bae
Nuclear Technology | Volume 183 | Number 3 | September 2013 | Pages 287-297
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A19418
Articles are hosted by Taylor and Francis Online.
The major roles of a prototype sodium-cooled fast reactor (SFR) planned to be developed at the Korea Atomic Energy Research Institute are (a) to provide an irradiation test capability for fuel and structural materials and (b) to obtain operational experience on the systems and components. The power level of the prototype SFR should be large enough to provide an appropriate irradiation test environment. Trade-off studies were therefore performed from a neutronics viewpoint to determine the power level. Specifically, core designs were performed for power levels of 125, 250, 400, and 500 MW(thermal). The selected core performance and economic efficiency indices became insensitive to the power at [approximately]400 to 500 MW(thermal) and sharply deteriorated at [approximately]125 to 250 MW(thermal) with decreasing core sizes. For the fuel management scheme, the transuranic (TRU) core performance compared with that of the uranium core, and the sodium void reactivity, were also evaluated with increasing power levels. It was found that increasing the number of batches shows a higher-burnup performance and economic efficiency. However, increasing the cycle length resulted in a lower economic efficiency. The irradiation performance of TRU and enriched TRU cores was improved by [approximately]20% and 50%, respectively. A maximum sodium void reactivity of 5.2 $ was confirmed as less than the design limit of 7.5 $. As a conclusion of our entire study, the power capacity of the prototype SFR should not be <250 MW(thermal), and would be appropriate at [approximately]500 MW(thermal) considering the performance and economic efficiency.