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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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.
Roberto Orsi
Nuclear Science and Engineering | Volume 157 | Number 1 | September 2007 | Pages 110-116
Computer Code Abstract | doi.org/10.13182/NSE07-A2716
Articles are hosted by Taylor and Francis Online.
This paper aims to stimulate research and to focus the attention of deterministic radiation transport code developers and users on further methodologies in transport analysis that some recent additions to the code package BOT3P potentially make possible in structured Cartesian or cylindrical mesh grids simulating complex geometries. In particular, BOT3P Version 5.0 can compute the possible area/volume error of material zones due to the stair-cased geometrical representation and automatically correct material densities in order to conserve masses, as described in a previous BOT3P paper published in Volume 154, Number 2 of Nuclear Science and Engineering to which the present one is logically and strictly related. When calculating areas and volumes refinements or when reducing the problem sizes of a voxelized geometry, typical of medical applications, BOT3P generates binary files that store also a fine submesh grid for each coarse cell at material interfaces. These files were originally conceived only for density correction computation and plotting purposes. However, the availability of such cell data intuitively suggests multistep transport analysis approaches that may combine detailed solutions at material interfaces with acceptable problem sizes and computational times. Reaching this appealing target could let deterministic codes based on structured mesh grid successfully deal with any challenging geometry problem. That might be particularly useful in medical and reactor applications.