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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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.
A. Bujan, B. Tóth, A. Bieliauskas, R. Zeyen, C. Housiadas
Nuclear Technology | Volume 169 | Number 1 | January 2010 | Pages 1-17
Technical Paper | Reactor Safety | doi.org/10.13182/NT10-A9339
Articles are hosted by Taylor and Francis Online.
Phébus FP tests study the phenomenology of severe accidents in water-cooled nuclear reactors. The first test, FPT0, was performed with fuel irradiated for only 1 week; the second test, FPT1, was performed with fairly similar boundary conditions but with irradiated fuel (burnup: 23 GWd/t). The objective of this work is, on the one hand, to summarize the main experimental results of these two tests concerning the behavior and transport of fission products and structural materials in the circuit and, on the other hand, to identify or to confirm any modeling weaknesses in the SOPHAEROS/ASTEC V1 module used for interpreting the experimental results. Besides comparison with available experimental data, the main results of the entire circuit analyses are compared with former SOPHAEROS/ASTEC V0 analyses and, for so-called quasi-separated steam generator tubes, with one- and two-dimensional Eulerian and Lagrangian (particle tracking) models.Concerning the transport of iodine vapor species, it is shown that the results obtained are compatible with passage of nonnegligible amounts of the measured highly volatile iodine through circuit to containment. It is also shown that these results depend heavily on the considered kinetics of Cd release from the bundle.