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Division Spotlight
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
2023 ANS Winter Conference and Expo
November 12–15, 2023
Washington, D.C.|Washington Hilton
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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Nuclear Science and Engineering
October 2023
Nuclear Technology
Fusion Science and Technology
Latest News
NRC moves ahead on HALEU enrichment, rulemaking, and guidance
The Nuclear Regulatory Commission is requesting comments on the regulatory basis for a proposed rule for light water reactor fuel designs featuring high-assay low-enriched uranium (HALEU), including accident tolerant fuel (ATF) designs, and on draft guidance for the environmental evaluation of ATFs containing uranium enriched up to 8 percent U-235. Some of the HALEU feedstock for those LWR fuels and for advanced reactor fuels could be produced within the first Category II fuel facility licensed by the NRC—Centrus Energy’s American Centrifuge Plant in Piketon, Ohio. On September 21, the NRC approved the start of enrichment operations in the plant’s modest 16-machine HALEU demonstration cascade.
L. El-Guebaly, M. Harb, A. Davis, J. Menard, T. Brown
Fusion Science and Technology | Volume 72 | Number 3 | October 2017 | Pages 354-361
Technical Paper | doi.org/10.1080/15361055.2017.1333864
Articles are hosted by Taylor and Francis Online.
The Fusion Nuclear Science Facility (FNSF) is viewed as an essential element of the US developmental roadmap to fusion energy. The spherical tokamak-based FNSF has been designed through a national collaborative effort led by the Princeton Plasma Physics laboratory. High-temperature superconducting (HTS) magnets are potentially attractive for such applications. Among other aspects, the magnet shielding and tritium breeding assessments represent key elements for achieving the design engineering objectives. Numerous inboard shielding and cooling materials have been examined to select an optimal shield that protects the inboard HTS magnet and in the meanwhile enhances the outboard breeding. The breeding blanket of choice is the dual-cooled lead lithium (DCLL) blanket. Our 3-D neutronics model included all blanket internals in great details along with nine specialized ports for blanket testing, materials testing, plasma heating, and current drive. The inclusion of a thin DCLL blanket on the inboard side was deemed necessary to achieve an overall tritium breeding ratio in excess of unity.