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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
J. Hardy, Jr., G. G. Smith, J. A. Mitchell, D. Klein
Nuclear Science and Engineering | Volume 12 | Number 2 | February 1962 | Pages 301-308
Technical Paper | doi.org/10.13182/NSE62-A26071
Articles are hosted by Taylor and Francis Online.
The Dancoff correction factor (1 − C) for U238 resonance neutron capture was measured for cylindrical, 0.98 cm diameter fuel rods at lattice pitches of 1.81 cm and 1.44 cm. The rods were 1.3% U235, arranged in a hexagonal, H2O-moderated lattice. Measurements were done for three fuel materials: uranium metal, UO2 (density 10.5 gm/cm3), and UO2 (density 7.5 gm/cm3) according to the following method. The ratio of U238 epicadmium neutron capture per atom at rod surface to that at rod center, S/V, was measured, for each fuel composition, at both lattice pitches and in an isolated rod (i.e., no Dancoff interaction). The quantity R ≡ [(S − V)/V]lattice/[(S − V)/V]isolated rod was, within experimental error, the same for all three fuel materials at each lattice pitch. Furthermore, within experimental error, R was found to be equal to (1 − C), calculated at each lattice pitch from Dancoff's expression. This agreement was expected from an analysis of the experiment in terms of a current model of resonance capture which indicated that R equals (1 − C) multiplied by two factors: one accounting for lattice mutual shielding of capture at rod center, the other accounting for the effect on S/V of the resonance flux lethargy tilt (due to loss of neutrons by resonance capture). Approximate calculations of these two effects showed that each perturbs R by about 10% in the worst case. The effects oppose each other so that very closely R = 1 − C.