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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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Penn State and Westinghouse make eVinci microreactor plan official
Penn State and Westinghouse Electric Company are working together to site a new research reactor on Penn State’s University Park, Pa., campus: Westinghouse’s eVinci, a HALEU TRISO-fueled sodium heat-pipe reactor. Penn State has announced that it submitted a letter of intent to host and operate an eVinci reactor to the Nuclear Regulatory Commission on February 28 and plans to engage with the NRC on specific siting decisions. Penn State already boasts the Breazeale reactor, which began operating in 1955 as the first licensed research reactor at a university in the United States. At 70, the Breazeale reactor is still in operation.
A. B. Reynolds, T. J. Thompson, K. M. Henry, E. B. Johnson
Nuclear Science and Engineering | Volume 7 | Number 1 | January 1960 | Pages 1-13
Technical Paper | doi.org/10.13182/NSE60-A25691
Articles are hosted by Taylor and Francis Online.
Reactivity effects of large voids in the reflector of the Pool Critical Assembly, an enriched-uranium, light-water-moderated and -reflected reactor, were investigated. The four reactivity effects studied were (1) variation of reactivity with void size, (2) variation of reactivity with void position on the core-reflector interface, (3) variation of reactivity with the distance between the void and the core, and (4) superposition of void reactivity effects. The variation of reactivity with void size and position on the core-reflector interface was correlated by a statistical weight correlation. An approximate theoretical method based on two-group diffusion theory was developed for calculating both the effect on reactivity and the effect on the neutron flux for a void covering one entire face of a reactor having a rectangular parallelepiped core. The calculated effects on reactivity and on the thermal-neutron fluxes were in reasonable agreement with experimental results.
