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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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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.”
B. F. Gore, B. R. Leonard, Jr.
Nuclear Science and Engineering | Volume 53 | Number 3 | March 1974 | Pages 319-323
Technical Note | doi.org/10.13182/NSE74-A23356
Articles are hosted by Taylor and Francis Online.
Calculations have been performed which indicate the possibility of reducing below ten years the effective half-life for transmutation of massive loadings of 137Cs placed in the blanket of a controlled thermonuclear reactor (CTR). The calculations assume the cylindrical “standard blanket” geometry and neutron source (which yields a vacuum wall loading of 10 MW/m2 of 14-MeV neutrons). Significant thermal flux enhancement is obtained by (n,2n) reactions in a beryllium moderator. Gas production and induced radioactivity problems in the beryllium moderator are not much worse than in a graphite moderator. For an 80% target-zone loading of 137Cs, a transmutation rate of 290 kg per year per meter of CTR length is obtained. At this loading, the transmutation rate in roughly 1% of the length of a CTR blanket would balance the production rate in a fission reactor of the same power. Constraint of the CTR source strength to yield a wall loading of 1 MW/m2 would increase the effective half-life for 137Cs to more than 20 years.