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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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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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Remembering Joseph M. Hendrie
Joseph M. Hendrie
To those of us who knew Joe, even prior to his appointment as chair of the Nuclear Regulatory Commission, it is an understatement to say that he was a larger-than-life member of the nuclear science and technology enterprise. He was best known to the broader community for two major accomplishments: the design and construction of the High Flux Beam Reactor (HFBR) at Brookhaven National Laboratory and the creation of the standard review plan (SRP) for the U.S. Atomic Energy Commission.
In addition to the products of these endeavors becoming major fundaments to their respective communities, they were uniquely Joe. The safety analysis report for the HFBR was written essentially single-handedly by him. This was true of the SRP as well, which became the key safety review document for the NRC as it performed safety reviews for the growing number of power reactor applications in the United States. His deep technical knowledge of nuclear engineering and his extraordinary management skills made this possible.
Enrico Lucon
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 289-294
Fusion Materials | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8916
Articles are hosted by Taylor and Francis Online.
Within the European Fusion Development Agreement (EFDA) Long Term Programme activities on Material Research, several versions of EUROFER ODS (Oxide-Dispersion Strengthened) have been produced and characterized. The most promising ones to date are the so-called "2nd generation" ODS (HIPped, hot rolled and thermomechanically treated) and the "EU batch" (produced by Plansee in the form of hot rolled plates and extruded bars). These two materials have been mechanically characterized in the unirradiated condition at SCKCEN in collaboration with other European institutes by means of tensile, impact and fracture toughness tests. The same characterization has been performed at SCKCEN on the two materials after low dose irradiation at 300°C in the BR2 test reactor (1.5-1.7 dpa). The results are compared with available data from early versions of EUROFER ODS and conventional (i.e. non-ODS) EUROFER, unirradiated and irradiated under similar conditions. It is confirmed that even the most advanced ODS steels show higher tensile strength than the base material, but also significantly worse fracture toughness properties. On the other hand, the "EU batch" irradiated to 1.52 dpa shows comparatively limited irradiation sensitivity.