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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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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
X-energy receives federal tax credit for TRISO fuel facility
Advanced reactor company X-energy has been awarded $148.5 million in tax credits under the Inflation Reduction Act for construction of its TRISO-X fuel fabrication facility in Oak Ridge, Tenn.
H. Zhang, A. Ying, M. Abdou
Fusion Science and Technology | Volume 68 | Number 2 | September 2015 | Pages 362-367
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-936
Articles are hosted by Taylor and Francis Online.
In this paper the problem of tritium transport in PbLi (Lead-Lithium) blankets has been studied and analyzed by means of our recently developed computational models. Several simulations are performed by incorporating the geometric configurations of the PbLi blankets including both DCLL (Dual Coolant Lead Lithium) and HCLL (Helium Cooled Lead Lithium) blankets. Tritium permeation loss percentage from the HCLL concept is about one order of magnitude higher than from the DCLL concept (~ 17%. vs. 1.2%). Sensitivity study also shows that the most relevant factors on tritium permeation are: 1) the level of tritium solubility in PbLi, 2) the gap velocity of the liquid metal in a DCLL blanket, 3) Hartmann number, and 4) the FCI (Flow Channel Insert) electrical conductivity.
