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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Alice Ying, Hongjie Zhang, Mu-Young Anh, Youngmin Lee
Fusion Science and Technology | Volume 68 | Number 2 | September 2015 | Pages 346-352
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-908
Articles are hosted by Taylor and Francis Online.
First-of-a-kind numerical simulation was performed to evaluate time dependent tritium transport properties for Korea’s HCCR (Helium-Cooled Ceramic Reflector) TBM (Test Blanket Module) design under ITER inductive operating conditions. The estimation of tritium inventories in various components of the HCCR submodule and its permeation amount into the helium coolant was obtained through three computational models involving: 1) a 3D FW standalone model where diffusion and permeation into FW He coolant through tritium ion implantation was studied, 2) a 2D Poloidal-Radial (P-R) mid-plane model where the effect of increased tritium concentration in the purge gas stream was accounted for, and 3) a 2D Toroidal-Radial (T-R) mid-plane model to study tritium concentration accumulation in the He coolant. The analysis shows that tritium inventory in the breeder reaches an equilibrium value in about 10 cycles, and is about 0.373 mg per submodule. Tritium inventory in the ferritic steel structure reaches its equilibrium value in less than 10 cycles, and has about 0.0012 mg per submodule at the end of the plasma burn. The amount of the tritium permeated into helium coolant is about 1.8% of the amount of tritium produced per cycle.