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The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
Strontium: Supply-and-demand success for the DOE’s Isotope Program
The Department of Energy’s Isotope Program (DOE IP) announced last week that it would end its “active standby” capability for strontium-82 production about two decades after beginning production of the isotope for cardiac diagnostic imaging. The DOE IP is celebrating commercialization of the Sr-82 supply chain as “a success story for both industry and the DOE IP.” Now that the Sr-82 market is commercially viable, the DOE IP and its National Isotope Development Center can “reassign those dedicated radioisotope production capacities to other mission needs”—including Sr-89.
Franz X. Gallmeier
Nuclear Science and Engineering | Volume 120 | Number 2 | June 1995 | Pages 102-109
Technical Paper | doi.org/10.13182/NSE95-A24111
Articles are hosted by Taylor and Francis Online.
A new option KCORR for calculating the eigenvalue keff of fission reactor arrangements has been implemented in the MCNP Monte Carlo code. This option is based on a matrix method and has the additional feature of applying correlated sampling methods to investigate small reactivity effects that are very likely lost in the statistical uncertainties of two independent program runs with the old option KCODE. For verification of the new program option, calculations of the reactivity worths of the control rod and the safety rod of the FOEHN reactor and the reactivity effects of various components in the reflector pool of the FOEHN reactor were performed with both KCODE and KCORR and compared with measured data. The efficiency of MCNP in calculating reactivity changes by using KCORR is improved not only by means of lower statistical uncertainties but also by reduction of computing time.