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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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.
V. M. Shmakov, V. D. Lyutov, V. A. Bekhterev
Nuclear Science and Engineering | Volume 145 | Number 2 | October 2003 | Pages 234-246
Technical Paper | doi.org/10.13182/NSE03-A2379
Articles are hosted by Taylor and Francis Online.
Effective neutron multiplication factors for 66 critical systems were calculated in order to test the neutron data library BAS. The class of systems chosen for the keff calculations includes unreflected metal uranium and plutonium systems and systems that were reflected by 238U, Fe, Al, Ti, Pb, Be, C, CH2, and H2O. Configurations and materials used in these critical systems were taken from the "International Handbook of Evaluated Criticality Safety Benchmark Experiments." The calculations with BAS were performed using the codes PRIZMA-D and MCNP.4a. For comparison, the calculations were repeated using MCNP.4a with ENDF/B5 and ENDF/B6 cross-section data. A comparison of all results is provided.
