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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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Fusion Science and Technology
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.
Sosuke Kondo, Keyong Hwan Park, Yutai Katoh, Akira Kohyama
Fusion Science and Technology | Volume 44 | Number 1 | July 2003 | Pages 181-185
Technical Paper | Fusion Energy - Fusion Materials | doi.org/10.13182/FST03-A330
Articles are hosted by Taylor and Francis Online.
High temperature and high dose irradiation effects on microstructural evolution in high purity -SiC was studied by Single- and dual-ion irradiation, where 5.1 MeV Si2+ ions for displacement damage and 1 MeV He+ ions for (n, ) simulation were implanted at 1673 K. From a cross-sectional transmission electron microscopy (XTEM) study of the -SiC irradiated with single-ion up to a dose of 100 dpa, high density dislocation loops were observed. Sizes and concentrations of the loops are dependant on displacement damage level. In the dual-ion irradiated specimen, dislocation network was observed through the dual-ion irradiated region. At the same time, cavities were formed in both the grain and grain boundary. In front of the irradiated surface, localized growth of the cavities was observed. TEM micrographs demonstrate that the helium had a large mobility on grain boundary and dislocation network under high temperature irradiation. It is clarified that helium largely contributes to the development of irradiation-induced microstructural defects. The formation mechanisms of microstructural defects were also discussed.