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This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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June 16–19, 2024
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Strong performances across the board
Craig Piercycpiercy@ans.org
Another year, another stellar performance by America’s nuclear plants. We’ve come to expect high capacity factors, and it’s a credit to the men and women of the profession. They’ve made routine something that was unimaginable not so long ago.
The decadal challenge for the nuclear enterprise now is to maintain this high level of operational excellence for the current fleet, while at the same time ushering in a new generation of technologies at scale. It will be a big job—but one that seems more and more likely with each passing day.
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.