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Nuclear Installations Safety
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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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
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.”
J. Chernick, S. Oleksa Moore
Nuclear Science and Engineering | Volume 6 | Number 6 | December 1959 | Pages 537-544
doi.org/10.13182/NSE59-A15516
Articles are hosted by Taylor and Francis Online.
The breeding potential of thermal reactors is re-evaluated on the basis of present nuclear data. It is concluded that positive breeding on the U233, thorium cycle is possible with a variety of moderators including heavy water, graphite, beryllium, and ordinary water. Current measurements indicate that the accepted thermal value of η23 = 2.28 ± 0.02 is somewhat conservative. Neutron spectrum considerations show that η23 decreases gradually with increasing resonance absorption to a minimum of 2.14 ± 0.04. When neutron losses to the moderator are considered, maximum breeding gains of 0.26, 0.22, 0.21, and 0.19, respectively, are obtained for D2O, graphite, Be, and H2O moderated reactors. The breeding gain in reactors partially or completely moderated by beryllium can be considerably increased if use is made of the fast effect, presently estimated at 1.075 ± 0.02 for pure beryllium. Probable breeding gains in proposed full-scale fluid fuel breeders are estimated at 0.09 for the Aqueous Homogenous Reactor and 0.05 for the graphite moderated Liquid Metal Fuel Reactor and Molten Salt Reactor. Breeding in predominantly thermal, solid fuel reactors also appears within reach if neutron losses are minimized. The possibility of positive breeding in near thermal, plutonium fuelled reactors is unsettled although this goal can be approached by maximum use of the fast effect in U238. Estimates of breeding ratios in plutonium fuelled reactors depends on the variation of η49 with neutron temperature which is still inadequately known.