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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.
B. M. Rothleder
Nuclear Science and Engineering | Volume 100 | Number 4 | December 1988 | Pages 479-489
Technical Paper | doi.org/10.13182/NSE88-A23581
Articles are hosted by Taylor and Francis Online.
Measurements made during cycle 1 operation of Commonwealth Edison Company’s Zion Unit 2 pressurized water reactor core were used to validate the Electric Power Research Institute Advanced Recycle Methodology Program. In addition to the usual reaction rate and axial trace measurements for determining power distributions, gamma scan measurements were available to provide additional data to validate the calculated power shapes. The parallel occurrence of gamma scan measurements and standard nuclear instrumentation measurements provided a unique opportunity to intercompare the results of these measurement methods. The calculated X-Y gamma scan behavior supported the behavior of the calculated X-Y reaction rates. The measured X-Y gamma scans were found to be more accurate than the measured X- Y reaction rates, with the latter showing significant differences among some symmetrically located assemblies. For both types of measurement, however, the modeling of the asymmetrically loaded assembly located furthest in the core periphery produced the poorest results. The axial gamma scan calculation proved very accurate except at the inlet and outlet regions.