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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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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. B. Rosenthal, E. A. Szymkowiak, C. H. George
Nuclear Technology | Volume 6 | Number 3 | March 1969 | Pages 191-198
Technical Paper and Note | doi.org/10.13182/NT69-A28305
Articles are hosted by Taylor and Francis Online.
An experiment was performed to study the dynamic control of a reactor by hydrogen transport and to demonstrate its load-following capabilities. The system is based on the mass transport of hydrogen between two ZrHX beds—one UO2 fueled, the other unfueled. The in-core hydrogen concentration controls the reactivity, and the resulting changes in reactor flux control the heat input into the in-core UO2-fueled bed. In turn, the in-core hydrogen concentration is controlled by changes in temperature differences between the in-core and out-of-core beds. Within analytical design constraints set by experimental and safety requirements, calculated ranges of parameters established design specifications. Preliminary validation measurements included reactor stability and temperature coefficient, experimental system stability and temperature coefficient, and in-core hydrogen worth. Comparison showed that hydrogen mass transport contributed 73% of the effectiveness of hydrogen reactivity control while temperature contributed only 27%. All experimental transient responses to step changes in thermal load exhibited analytically predicted damped oscillatory behavior. Reactor startup, shutdown, and response to reactivity changes were demonstrated. This experiment verified that hydrogen reactivity control, a mechanically passive device, is an effective, self-regulating mechanism for controlling a nuclear reactor.