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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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.
D. Rochman, A. J. Koning, D. F. Da Cruz
Nuclear Technology | Volume 179 | Number 3 | September 2012 | Pages 323-338
Technical Paper | Fission Reactors/Fuel Cycle and Management | doi.org/10.13182/NT11-61
Articles are hosted by Taylor and Francis Online.
The effects of nuclear data uncertainties (cross sections, neutron emissions, fission yields, and decay data) on the burnup of a typical pressurized water reactor fuel element are presented in this paper. The uncertainties on reactivity swing, inventory, and radiotoxicity are obtained using a Monte Carlo method for nuclear data uncertainty propagation and the Monte Carlo transport code SERPENT. The impact of the nuclear data uncertainties for the two main actinide isotopes at the beginning of irradiation (235U and 238U) with the third and fourth most abundant actinide isotopes at the end of irradiation (236U and 239Pu) are calculated, showing the importance of fission yield data relative to transport data.