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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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2020 ANS Virtual Winter Meeting
November 15–19, 2020
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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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Fusion Science and Technology
Latest News
NRC schedules webinars on Holtec’s proposed New Mexico storage site
The Nuclear Regulatory Commission has scheduled four webinars in late August and early September to present its draft environmental findings and receive comments on Holtec International’s proposed consolidated spent nuclear fuel storage facility in New Mexico. Webinars were previously held on June 23 and July 9.
As published in the August 13 Federal Register, the public comment webinars will be held on August 20 from 6–9 p.m., August 25 from 2–5 p.m., August 26 from 6–9 p.m., and September 2 from 11 a.m.–2 p.m. All times are Eastern. Information for the webinars is posted on the NRC’s Public Meetings webpage.
Javier Sanz, Rafael Falquina, Arturo Rodriguez, Oscar Cabellos, Susana Reyes, Jeffery F. Latkowski
Fusion Science and Technology | Volume 43 | Number 3 | May 2003 | Pages 473-477
Technical Paper | Safety and Environment | dx.doi.org/10.13182/FST03-A293
Articles are hosted by Taylor and Francis Online.
The global effect of activation cross-section uncertainties on calculated radiological quantities is investigated for the first time using a methodology based on Monte Carlo random sampling. The method is applied to the calculation of the uncertainty in the contact dose rate from the gunite shielding of the National Ignition Facility chamber after 30 yr of pulsed irradiation. Some critical cross section contributing significantly to the overall uncertainty are identified. By a reasonable reduction of the uncertainty in those cross sections, the accuracy in the calculated total contact dose rate is greatly improved.
