ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
R.A. Causey, K.L. Wilson, W.R Wampler, B.L. Doyle
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1585-1588
Material and Tritium | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29567
Articles are hosted by Taylor and Francis Online.
For the next generation of fusion reactors, tritium inventory will be one of the greatest safety concerns. Both CIT and ITER call for the use of graphite or carbon composites as the first wall and divertor material. If this graphite should contain a large number of traps for the storage of tritium, the resulting inventory could restrict the operation of the reactor. This report presents the results of an experimental study on the effects of neutron irradiation on the trapping of tritium in graphite. Enhancements in the trapping levels by two orders of magnitude up to as high as 0.2 atomic percent were seen for graphite samples irradiated to approximately 10 dpa at different temperatures. The results are compared to those obtained for ion damaged samples. The implications of the results for the operation of CIT and ITER are examined.
