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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.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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.
A. W. Gray
Nuclear Technology | Volume 12 | Number 4 | December 1971 | Pages 342-347
Technical Paper | Reactor | doi.org/10.13182/NT71-A30982
Articles are hosted by Taylor and Francis Online.
An analytical study has been completed to define minimum critical mass parameters for a spherical region containing a 235U-H2O mixture reflected by a natural uranium-water mixture. The study indicates that for an optimum natural-H2O reflector, the calculated minimum critical mass for the central sphere lies in the range of 75 to 200 g of 235U. The analytic study was divided into three phases. In the first phase homogeneous two-region systems were examined using diffusion theory programs. The results indicated a minimum critical mass of 451-g 285U for an optimal system. In the second phase a Monte Carlo program was utilized to compute keff for uranium metal rod-H2O moderated lattices for which experimental data are available. The purpose of the second phase was to establish the validity of the Monte Carlo program as an analytical tool. In the third phase the Monte Carlo program was used to calculate 235U + H2O spheres closely reflected by an optimum lattice of natural uranium rods. The Monte Carlo program indicates that the minimum critical mass in an H2O-moderated system reflected by a uranium metal lattice is 135 ± 65 g 235U.