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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
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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.
R. E. Maerker, F. J. Muckenthaler, R. L. Childs
Nuclear Technology | Volume 22 | Number 2 | May 1974 | Pages 275-297
Shielding | doi.org/10.13182/NT74-A31409
Articles are hosted by Taylor and Francis Online.
An experiment concerning deep neutron penetration in sodium was performed, and experimental results were obtained which provide a basis for verification of the accuracy of sodium cross sections to be used in transport calculations. The experiment was conducted at the Tower Shielding Facility of Oak Ridge National Laboratory and included measurements of both the neutron fluence and the neutron spectra through a large diameter sample of sodium up to 15 ft thick. Calculated results for the experiment were also compared with the experimental measurements. These results were obtained using the multigroup Monte Carlo code, MORSE, and a two-dimensional discrete ordinates code, DOT-III. One-hundred group data sets were developed from both a preliminary and the final version of the ENDF/III set (MAT-1156) for sodium for use in the calculations. Comparisons of the calculations with experiment indicate that (a) the preliminary version is slightly superior to the final version and (b) using the preliminary set, the total neutron leakage above thermal energies penetrating through 15 ft of sodium agrees to within ∼15%; and the absolute spectra penetrating through 12.5 ft of sodium, when integrated over the energy range of the measurement, agrees to within 20%. Using the final set, the corresponding comparisons are 30% and 60%.