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Division Spotlight
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.
R. N. Davie, Jr., J. F. Davis III, R. T. Schneider
Nuclear Technology | Volume 31 | Number 2 | November 1976 | Pages 276-278
Technical Note | Material | doi.org/10.13182/NT76-A31690
Articles are hosted by Taylor and Francis Online.
Optical components made of α -AI2O3 (synthetic sapphire) are used in optical systems (nuclear-pumped lasers, fission cells, etc.) to operate in a reactor in-core environment. Absorption and luminescence, which may take place in windows or lenses exposed to a reactor environment, will falsify results of optical measurements. For this reason, the knowledge of radiation-induced properties of optical materials is necessary. Measurements concerning optical absorption and luminescence of reactor-irradiated commercially available sapphire were made. The observed luminescence exhibits peaks around 3300 and 4100 Å The 3300-Å. peak increases as a function of irradiation time and saturates after 30 h of irradiation. The 4100-Å peak decreases monotonically. The absorption coefficient after 69 h of irradiation was measured. It ranges from 7 cm−1 at 3000 Å to 0.5 cm−1 at 6000 Å.