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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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.
Daniele Tomatis
Nuclear Science and Engineering | Volume 193 | Number 6 | June 2019 | Pages 622-637
Technical Paper | doi.org/10.1080/00295639.2018.1553428
Articles are hosted by Taylor and Francis Online.
The cross section preparation for reactor calculations produces few-group data libraries whose storage needs in memory increase severely when more physical output is requested. As a matter of fact, depletion chains with many isotopes are suggested for a more accurate isotopic inventory all along the fuel cycle, and coarse meshes are not suitable to compute finer distributions of reaction rates in highly heterogeneous systems. This work investigates the use of compression techniques on the power form factors to evaluate potential storage reduction for homogenized pin-by-pin data. The form factors are analyzed in several physical conditions of normal operation for Gd-poisoned UO2 and mixed-oxide fuel assemblies whose specifications come from a benchmark problem. Two numerical transforms are studied on two different applications, providing recommendations for general use in core calculations.