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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.
R. E. Maerker
Nuclear Science and Engineering | Volume 96 | Number 4 | August 1987 | Pages 263-289
Technical Paper | doi.org/10.13182/NSE87-A16391
Articles are hosted by Taylor and Francis Online.
A second example of applying the LEPRICON methodology to an existing pressurized water reactor is described. The present application is an analysis of ad hoc dosimetry inserted into the H. B. Robinson-2 reactor to monitor the effects on pressure vessel fluence produced by the introduction of a low-leakage fuel management scheme during cycle 9. The use of the simultaneous dosimetry at both a downcomer location and in the reactor cavity allowed a quantitative evaluation to be made by the LEPRICON procedure of the relative merits of each location. Unfolded results using the dosimetry indicate that the cumulative neutron fluence above 1 MeV originally calculated for the critical lower circumferential weld of the pressure vessel during cycle 9, 7.2 × 1017 n/cm2± 15.9%, should be adjusted upward by about one standard deviation to a value of 8.8 × 1017 n/cm2 with a reduced uncertainty of 10.9%.