ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Education, Training & Workforce Development
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.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
Standards Program
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
Nuclear supply chain innovation and collaboration: Keeping the nuclear supply chain viable through change
The next nuclear renaissance may be upon us, but with it comes a perfect storm. The industry is unprepared for a surge in demand for goods and services from both the existing light water fleet and the next generation of reactors. We are currently teetering on the edge of severe supply chain issues, but if the nuclear industry can understand the sources of our challenges, we can mitigate them.
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.