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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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
Tank waste operations resume at Idaho’s IWTU
The Department of Energy’s Office of Environmental Management announced yesterday that waste processing operations have resumed at the Integrated Waste Treatment Unit (IWTU) at the Idaho National Laboratory Site. The resumption of operations follows the completion of two maintenance campaigns at the radioactive liquid waste treatment facility.
Edward J. Waller, Jason T. Brown
Nuclear Technology | Volume 175 | Number 1 | July 2011 | Pages 93-104
Technical Paper | Special Issue on the 16th Biennial Topical Meeting of the Radiation Protection and Shielding Division / Radiation Transport and Protection | doi.org/10.13182/NT11-A12276
Articles are hosted by Taylor and Francis Online.
Handling radioisotope neutron sources may involve exposure to both neutron and gamma fields. Although the field of gamma dosimetry is well developed and reliable, challenges exist with personal neutron dosimetry. A number of gamma and neutron dosimeters were evaluated for their efficacy in providing personal dosimetry for radioisotope source manipulations. A commercial off-the-shelf electronic neutron dosimeter was observed to underestimate total operator dose when manipulating a 252Cf source. In this work, scaling factors were evaluated using both experimental results and Monte Carlo simulations to allow a measured electronic personal gamma dosimeter (EPGD) dose to be used to estimate the total neutron + gamma dose. The recommended scaling factor using an MGP SOR/R EPGD for free-field 252Cf is 18, and for shielded 252Cf the recommended scaling factor is 6. A conservative single scaling factor of 18 is appropriate for personal dosimetry estimates.