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Division Spotlight
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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.
C. K. Tzou, C. M. Yang
Nuclear Technology | Volume 24 | Number 2 | November 1974 | Pages 246-251
Technical Paper | Analysis | doi.org/10.13182/NT74-A31480
Articles are hosted by Taylor and Francis Online.
A cold fuel assay method has been developed for nondestructive burnup determination by gamma-ray spectroscopy. This method utilizes the product of neutron flux and time as one variable to avoid tedious treatment of neutron flux, resident time, and intermittent type of iteration. No chemical or mass spectroscopic analysis is needed; only the photopeak of 137Cs needs to be analyzed. The method has been applied to fuel element No. 25 of the Tsin-Hua open-pool reactor for burnup calculation. A 35-cm3 Ge(Li) detector connected to a 1024 MCA was used.
