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Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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A day in the life of the nuclear community
The November issue of Nuclear News is focused on the individuals who make up our nuclear community.
We invited a small group of those individuals to tell us about their day-to-day work in some of the many occupations and applications of nuclear science and technology, and they responded generously. They were ready to tell us about the part they play, together with colleagues and team members, in supplying clean energy, advancing technology, protecting safety and health, and exploring fundamental science.
In these pages, we see a community that can celebrate both those workdays that record progress moving at a steady pace and the exceptional days when a goal is reached, a briefing is delivered, a contract goes through, a discovery is made, or an unforeseen challenge is overcome.
The Nuclear News staff hopes that you enjoy meeting these members of our community—or maybe get reacquainted with friends—through their words and photos.
David L. Aumiller, Michael J. Meholic
Nuclear Science and Engineering | Volume 184 | Number 3 | November 2016 | Pages 441-452
Technical Paper | dx.doi.org/10.13182/NSE16-41
Articles are hosted by Taylor and Francis Online.
An assessment of the predictive capability of Coolant Boiling in Rod Arrays–Integrated Environment (COBRA-IE) for critical heat flux (CHF) using the 2005 Groeneveld CHF lookup table is presented. The assessment was performed against 13 different open literature CHF experiments that were conducted over a wide range of conditions in various internal flow geometries. Overall, approximately 1300 data points were evaluated.
Different methodologies to quantify the uncertainty inherent in the CHF models are discussed in this paper. The simulation techniques, uncertainty methods, and results of two of the methods are provided. A discussion of the appropriate use of the CHF uncertainty methods is included. The results indicate that for the method associated with the largest uncertainty, the average measured/predicted value in CHF is 1.19, and the standard deviation is 0.62. For the second method, similar to the critical power ratio used for boiling water reactors, the average ratio is 0.98, and the standard deviation is 0.13. Finally, a method to translate between the methods is proposed and shown to be accurate. The use of this transformation could permit significant time and cost savings by allowing a single uncertainty assessment to serve two very different analytical needs.