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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Josselin Morand, Reinhard Hentschel, Andrea Wittig, Raymond Moss, Sabet Hachem, Yuan-Hao Liu, Wolfgang Sauerwein
Nuclear Technology | Volume 168 | Number 2 | November 2009 | Pages 456-461
Shielding | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 2) / Radiation Protection | doi.org/10.13182/NT09-A9224
Articles are hosted by Taylor and Francis Online.
Monte Carlo simulation of accelerated ions is a standard method in radiation protection. Such simulations have been used to calculate photon and neutron production in a beryllium target of the Essen d(14)+Be Fast Neutron Therapy Facility. In the deuteron case the predominant part of the neutrons is produced by breakup of the input particle, a decay that is not foreseen in standard versions of Monte Carlo codes. Thus, the calculation yields results that are different from measured ones. For simulations of the neutron beam at such facilities, an input description containing the spectral and geometric properties of the neutron and eventually photon beams produced in the target is needed. For the Essen neutron beam, such a description has been obtained by comparison of MCNPX simulations with published data and measurements at a static beam geometry having no background radiation. The validation of the neutron beam input description was obtained by comparing measured and calculated dose distributions in a water phantom using a standard collimator at the treatment gantry.