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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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.
L. F. Miller, R. G. Cochran, J. W. Howze
Nuclear Technology | Volume 36 | Number 1 | November 1977 | Pages 93-105
Radiation Environments in Nuclear Reactor Power Plant | Reactor | doi.org/10.13182/NT77-A31963
Articles are hosted by Taylor and Francis Online.
The problem of designing a constrained feedback control system for a nuclear reactor is investigated. The constraint imposed is that system stability must be retained under possible loss of any arbitrary feedback signal due to failure of the signal sensor. In addition, the control law is synthesized using only partial state availability, and the nominal control system without sensor failure is designed so that the system performs in a desired fashion. Several mathematical models of the reactor dynamics were employed. However, only a model with negative moderator activity coefficients and a single delayed neutron group was used as an example. This model permits a demonstration of two different computational methods for obtaining the required feedback control laws. The first of these two computational methods uses a global procedure for solving polynomial inequalities that represent the stabilization problem. The second method used an algorithm for decreasing a spectral radius function until it is negative, thus allowing implicit control over eigenvalue placement.