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Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
W. Baer, J. Hardy, Jr., D. Klein, J. J. Volpe, B. L. Palowitch and F. S. Frantz, Jr.
Nuclear Science and Engineering | Volume 23 | Number 4 | December 1965 | Pages 361-367
Technical Paper | doi.org/10.13182/NSE65-A21073
Articles are hosted by Taylor and Francis Online.
Parameter measurements in a 1.3% enriched UO2 lattice with H:U = 0.42 have been performed. These measurements are an extension of an experimental program in the TRX critical facility of the Bettis Atomic Power Laboratory. Earlier measurements were made for a wide range of water-to-uranium (H2O:U) volume ratios (1:1 to 8:1) using 4-ft (1.2-m)-high slightly enriched, 0.387-in. (0.98-cm)-diam uranium metal or oxide fuel rods clad with aluminum. The new data have been compared with current analytic techniques, using both P-1 and P-3 multigroup analysis in the epithermal neutron energy range and Monte Carlo multigroup methods for thermal neutrons. This extremely undermoderated lattice provides a very stringent test for both the computational methods and the neutron cross sections used. The quantities measured were: the ratio of epithermal-to-thermal radiative captures in U238 (ρ28); the ratio of captures in U238 to fissions in U235 (the modified conversion ratio, CR*); the ratio of U238 fisions to U235 fissions (δ28); and the ratio of epithermal-to-thermal U235 fissions (δ25). In addition, activations were obtained with thermal-neutron detectors of widely different spectral response. The results indicate that the calculational methods predict the parameters very well, except for δ28. The discrepancy in δ28 may be due to inadequate U238 inelastic scattering cross sections, but this conclusion requires additional study. Monte Carlo calculations of thermal-neutron detector activations show that use of either the Nelkin or Koppel kernel gives results that agree with the data.