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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.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Fermilab center renamed after late particle physicist Helen Edwards
Fermi National Accelerator Laboratory’s Integrated Engineering Research Center, which officially opened in January 2024, is now known as the Helen Edwards Engineering Center. The name was changed to honor the late particle physicist who led the design, construction, commissioning, and operation of the lab’s Tevatron accelerator and was part of the Water Resources Development Act signed by President Biden in December 2024, according to a Fermilab press release.
Eliseo Visca, A. Pizzuto, B. Riccardi, S. Roccella, G. P. Sanguinetti
Fusion Science and Technology | Volume 61 | Number 2 | February 2012 | Pages 118-123
Technical Paper | First Joint ITER-IAEA Technical Meeting on Analysis of ITER Materials and Technologies | doi.org/10.13182/FST12-A13376
Articles are hosted by Taylor and Francis Online.
ENEA and Ansaldo Nucleare S.p.A. (EA) have been deeply involved in the European International Thermonuclear Experimental Reactor (ITER) research and development activities for the manufacturing of high-heat-flux plasma-facing components and in particular for the inner vertical target (IVT) of the ITER divertor.These components have to be manufactured by using both armor and structural materials whose properties are defined by ITER. Their physical properties prevent the use of standard joining techniques. The reference armor materials are tungsten and carbon/carbon fiber composite (CFC), and for the cooling pipe, the materials are a copper alloy (CuCrZr).During the last years EA have jointly manufactured several actively cooled mock-ups and prototypical components of different lengths, geometries, and materials by using innovative processes: hot radial pressing (HRP) and prebrazed casting (PBC).The HRP technique is based on radial diffusion bonding between the cooling tube and the armor material obtained by pressurizing only the cooling tube while the joining zone is kept in vacuum and at the required bonding temperature. The heating is obtained by a standard air furnace.The PBC process is used for the CFC armor tile preparation. A soft copper interlayer between the tube and armor is necessary to mitigate the stress at the joint interface, and it is obtained by pure copper casting that follows the activation of the CFC surface by a standard brazing alloy.The optimization of the processes started from the successful manufacturing of both tungsten and CFC small-scale mock-ups and successful testing under the worst ITER operating condition (20 MW/m2) through the achievement of record performances obtained from a medium-scale vertical target CFC and tungsten armored mock-up: After ITER-relevant heat flux fatigue testing (20 MW/m2 for 2000 cycles, CFC part, and 15 MW/m2 for 2000 cycles, tungsten part), it reached a critical heat flux of 35 MW/m2 at ITER-relevant thermal-hydraulic conditions.Based on these results EA participated in the European program for the qualification and manufacturing of the divertor IVT, according to the Fusion for Energy (F4E) specifications. A divertor IVT prototype (400-mm total length) with three plasma-facing-component units was successfully tested at ITER-relevant thermal heat fluxes (20 MW/m2 for 3000 cycles, CFC part, and 15 MW/m2 for 3000 cycles, tungsten part).Now, EA are ready to face the challenge of the ITER IVT production, transferring to an industrial production line the experience gained in the development, optimization, and qualification of the PBC and HRP processes.
