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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.
B. S. Moon, K. R. Kim, J. S. Moon, S. B. Kim
Nuclear Science and Engineering | Volume 122 | Number 3 | March 1996 | Pages 417-422
Technical Paper | doi.org/10.13182/NSE96-A24176
Articles are hosted by Taylor and Francis Online.
Equipment that is one-tenth the size of the steam generators for the Westinghouse 900-MW(electric) nuclear power plants is used to study the swell and shrinkage of the water level. The cyclic aspect of level swell and shrinkage occurring during low-power operation of the nuclear power plants is realized by sequential steam dump valve control. Experimental results show that a simple mathematical model based on the amount of steam generated during depressurization provides a good approximation for predicting level swell and shrinkage. Steam generation also causes water movement between the downcomer area and the inner part of the vessel, the effect of which during the initial steam dump period is estimated and applied to adjust this model.