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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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Latest News
Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
H. S. Bailey, R. N. Evatt, G. L. Gyorey, C. P. Ruiz
Nuclear Technology | Volume 17 | Number 3 | March 1973 | Pages 217-224
Technical Paper | Fuel | doi.org/10.13182/NT73-A31265
Articles are hosted by Taylor and Francis Online.
An evaluation of the radiation from higher exposure light water reactor fuel that is of significance in shipping container design has been made. Because these fuels contain significant quantities of transplutonium nuclides, it has been established that the neutron emission rate and the associated biological dose rate are of large enough magnitude to require special consideration in the shielding design. This analysis is based on experimental determination of heavy element nuclide concentrations in both PWR and BWR fuels and the use of ANISN-type shielding calculations. The results indicate that a conventional cask would not have sufficient neutron shielding capability to permit shipment of spent fuel with exposures in excess of ∼22 000 MWd/MT. Hence, a new generation of shipping casks with specific provisions for neutron shielding is required.