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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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. C. Burkholder, E. L. J. Rosinger
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 150-158
Technical Paper | Nuclear Power Reactor Safety / Radioactive Waste | doi.org/10.13182/NT80-A32516
Articles are hosted by Taylor and Francis Online.
The one-dimensional transport of radionuclides and their decay products from an underground nuclear waste isolation site through the surrounding geologic media to a surface environment is modeled. An ambiguity in the application of the previously reported mathematical solution for this problem has been clarified. The results of applying the solution described here compare favorably with the results of applying the former solution, but the present solution is computationally more efficient and less subject to numerical errors. Thus, this solution is presently being used by the authors and others to evaluate the sensitivity of potential radioactivity releases into the environment to the characteristics of various nuclear waste isolation systems. The model is expected to be used in the future as an analytical standard to which the accuracy of numerical codes can be compared.