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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
C. Z. Serpan, Jr.
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 108-118
Technical Paper | Material | doi.org/10.13182/NT71-A15903
Articles are hosted by Taylor and Francis Online.
A simulated vessel wall environment was constructed that provided for measurements of steel embrittlement increase and neutron flux detector activation at two typical surveillance program locations, as well as at five additional locations, through the thickness of an 8-in.-thick steel “vessel wall.” Neutron spectra for these locations were calculated using one transport and two diffusion theory reactor physics spectrum codes plus a multiple-foil spectrum analysis code. The measured increases in steel transition temperature from the experimental locations revealed the expected gradient of highest embrittlement near the core to least embrittlement at the outer edge of the simulated vessel. Good agreement with published trends was observed. Comparisons of the code calculations versus measurements of the decrease in fluence level between locations, however, were favorable only over the shortest distances. Neutron fluences for the critically important region between fuel core and pressure vessel inner edge were significantly higher from a multiple-foil spectrum analysis code than from transport and diffusion codes when based on comparisons of spectrally adjusted iron activation measurements. This evidence of the possibility that the real fluence values in the pressure vessel wall environment are higher than those produced by common measurement techniques suggests the need for reevaluation of current surveillance data, improvements in reactor physics codes, and continuing assessments of measured versus calculated surveillance fluence data.