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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
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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Latest News
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.
H. O. Menlove, C. D. Tesche, M. M. Thorpe, R. B. Walton
Nuclear Technology | Volume 6 | Number 4 | April 1969 | Pages 401-408
Technical Papers and Note | doi.org/10.13182/NT69-A28350
Articles are hosted by Taylor and Francis Online.
A resonance self-indication technique, that measures nondestructively the thickness of fissile materials, has been investigated. This method utilizes the resonance structure in the neutron fission cross section by passing an epithermal beam of neutrons through the sample and then to thin fission detectors that are sensitive to the resonance absorption lines in the transmitted flux corresponding to the resonance reaction peaks. The measurements included samples of 283U, 235U, and 239Pu with thicknesses ranging from 5 to 270 mils. The present measurements indicate that this technique could be used to measure the thickness of 239Pu with an accuracy of 1 to 3%, and an accuracy of 2 to 10% for 233U and 235U for thicknesses <150 mils. The influence of extraneous material in the samples was greatly reduced by using ratios of different fission detectors in the measurement. Computer calculations of the fission rates were made, and the theoretical results are in good agreement with the measurements.