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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
Standards Program
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
Proposed rule for more flexible licensing under Part 53 is open for comment
The Nuclear Regulatory Commission has published a proposed rule that has been five years in the making: Risk-Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors. The rule, which by law must take its final form before the end of 2027, would let the NRC and license applicants use technology-inclusive approaches and risk-informed, performance-based techniques to effectively license any nuclear technology. This is a departure from two licensing options with light water reactor–specific regulatory requirements that applicants can already choose.
M. Drosg, R. Avalos Ortiz, P. W. Lisowski
Nuclear Science and Engineering | Volume 172 | Number 1 | September 2012 | Pages 87-101
Technical Paper | doi.org/10.13182/NSE11-66
Articles are hosted by Taylor and Francis Online.
Much of the absolute differential cross-section data for elastic scattering by 3He depends on an experiment at the Los Alamos National Laboratory (LANL), published in 1974. Since that time, computer techniques have been developed that can make more accurate corrections for, e.g., sample-size effects. Since complete documentation of the LANL experiment is available, modern analysis techniques were applied to improve these data, based on simulations using the Los Alamos Monte Carlo neutron transport code MCNPX. Of a total of 29 published differential cross-section distributions, 15 published in 1982 from another laboratory depend on the LANL data but were not corrected for sample-size effects and therefore provide only relative yield functions. The present study simulates these latter data using MCNPX to obtain self-attenuation correction factors for the scattered neutrons. An energy-dependent analysis shows that at neutron energies between 5 and 14 MeV, these latter corrected data are in good agreement with the other data, whereas above 22 MeV they are not. A complete energy-dependent analysis of all absolute differential cross sections between 5 and 23.7 MeV is presented.