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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
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.
