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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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.
Gasper Zerovnik, Luka Snoj, Matjaz Ravnik
Nuclear Science and Engineering | Volume 163 | Number 2 | October 2009 | Pages 183-190
Technical Paper | doi.org/10.13182/NSE163-183
Articles are hosted by Taylor and Francis Online.
We demonstrated the use of combinatorial methods to optimize the filling of spent nuclear fuel (SNF) in metal canisters for final deep SNF repository, according to the maximal allowed thermal power per canister Pmax and the limit of n = 4 spent-fuel assemblies per canister. As a next step, the deposition time can be optimized by minimizing the required number of canisters M and the interim storage time. The method has been tested in detail for a typical pressurized water reactor (PWR), nuclear power plant (NPP) Krsko, SNF for different numbers of reactor cycles and different Pmax. The results show that the time interval between the last reactor cycle and the optimal deposition time varies between 3 and 30 yr for a typical PWR. The most significant contribution to the uncertainty of the calculated SNF decay heat (thermal power) is due to inaccurate cross sections taken from generic cross-section libraries. The quality of the results was verified by comparing the calculated M to the theoretical lower boundary Mmin. The idea behind the optimization method is universal and thus can be implemented for any SNF, canister, and repository design.