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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.
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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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.
Samuel H. Levine
Nuclear Technology | Volume 53 | Number 3 | June 1981 | Pages 303-325
Technical Paper | Nuclear Fuel Cycle Education Module / Education | doi.org/10.13182/NT81-A32641
Articles are hosted by Taylor and Francis Online.
This educational module utilizes techniques used to calculate the core reactivity, power distribution, and isotopic inventory for the first and subsequent cores of a nuclear power plant to maintain adequate safety margins and operating lifetime for each core. Some reloading schemes studied minimize energy costs. The module is written more for classroom presentation and self-study by students than for the practicing nuclear engineer; however, the first two sections cover in-core fuel management in a way that should be helpful to a utility manager having the purview of core analysis. The major emphasis is on light water reactors, but in-core fuel management for the high temperature gas-cooled reactor and the liquid-metal fast breeder reactor is included. The module involves detailed information on the systematic application of nucleonic codes, e.g., cross-section generating codes and nodal and diffusion theory multigroup codes, to calculate the depletion and reloading of nuclear power reactors. It is not intended to be a reactor physics text, but detailed derivations of formulas, e.g., the B1 approximation in LEOPARD, FLARE recursion formula, used in the relevant nucleonic codes, are given in greater detail than normally found in a text to eliminate the “black box” use of computer codes.