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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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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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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.
Hilbert Christensen
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 358-364
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT06-A3768
Articles are hosted by Taylor and Francis Online.
A previously developed radiolysis model has been used to simulate experiments from four laboratories. The source strengths in the experiments with UO2, doped with 238Pu, were 0.01, 0.1, and 1 Ci/g. The agreement was good with the experimental results of Stroes-Gascoyne et al. for their sample with 0.1 Ci/g. Their sample containing 0.01 Ci/g gave a factor-of-3-higher calculated corrosion rate compared with the experimental rate. In the experiments of Cobos et al. and of Kelm and Bohnert, using alpha-doped UO2, the calculated corrosion rates were somewhat lower than the experimental rates. However, recent experiments by Rondinella et al. using UO2 with 10% doped 233U gave considerably lower corrosion rates in good agreement with the model. The calculated corrosion rates for the same source strength were about the same for the experiments by Stroes-Gascoyne et al., Kelm and Bohnert, and Cobos et al. However, the experimental rates varied considerably. The agreement was not good with experiments using Pu(VI) dissolved in solution, in which case the calculated corrosion rate was ten times or more than ten times lower than the experimental rate. The reason for this disagreement could be a chemical effect of Pu(VI) in the solution.