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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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.
Yi Xu, Hong Li, Feng Xie, Jianzhu Cao, Jiejuan Tong
Fusion Science and Technology | Volume 71 | Number 4 | May 2017 | Pages 671-678
Technical Note | doi.org/10.1080/15361055.2017.1290949
Articles are hosted by Taylor and Francis Online.
The Very High Temperature Reactor (VHTR) is one of the six proposed Generation IV reactor concepts. The HTR-10, a 10 MW high temperature gas-cooled reactor was a helium cooled, graphite-moderated, and thermal neutron spectrum reactor. Since tritium (H-3) has an effect on the environment and public radiation dose, it has received more and more attention in the environmental impact assessment of nuclear facilities. Recently, several experiments on source terms in HTR-10 have been run, of which preliminary measurements indicated H-3 was an important nuclide in the primary loop of HTR-10. The production mechanism, distribution characteristic, reduction route, and release type of total H-3 in HTR-10 were analyzed and discussed in this technical note. A theoretical model was established to calculate the total activity of H-3 in the reactor core and activity concentration of H-3 in the primary loop of HTR-10. This model indicated that the majority of total H-3 was produced by ternary fission reactions and H-3 in the primary helium was mainly generated from activation reactions of impurities in the reactor core. The research results can provide useful information for the experimental measurement of H-3 in HTR-10, and promote the study of H-3 in high temperature gas-cooled reactors (HTGRs).