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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.
L. C. Longoria, J. C. Palacios, J. Santos
Nuclear Science and Engineering | Volume 133 | Number 2 | October 1999 | Pages 213-217
Technical Paper | doi.org/10.13182/NSE99-A2083
Articles are hosted by Taylor and Francis Online.
Measurements of gamma emission rates from Fe and Cu dosimeters extracted from a boiling water reactor-type reactor vessel were carried out to determine their total activity. The dosimeter's activity is related to the neutron flux at that location by taking into account the reactor material's embrittlement caused by neutron bombardment. The dosimeters were taken out after the first reactor operation cycle. From gamma radioactivity measurements of these dosimeters, neutron flux and fluence were calculated. These parameters are used in the determination of the shift and adjusted reference temperature values needed for the development of pressure-temperature curves used during reactor operation.
