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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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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.
C. K. Cheng, B. M. Ma
Nuclear Science and Engineering | Volume 48 | Number 2 | June 1972 | Pages 139-158
Technical Paper | doi.org/10.13182/NSE72-A22467
Articles are hosted by Taylor and Francis Online.
The time-dependent radius of the central void and the extents of the columnar grain, the equiaxed grain, and the unaffected grain regions of a typical oxide cylindrical fuel rod in a fast reactor at constant power level are determined. The temperature distributions in the fuel element are obtained. A model postulated to analyze and calculate the irradiation swelling and fission-gas release for oxide fuels of fast reactors is developed. The mechanical analysis is based on the thermal and radiation dilatations and on an elastoplastic approach for the Prandtl-Reuss material. An iteration method of successive approximation is used to compute the stresses and strains developed in the fuel elements. The computed results are shown by curves for the unsteady-state fuel restructuring of the fuel element.