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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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How to talk about nuclear
In your career as a professional in the nuclear community, chances are you will, at some point, be asked (or volunteer) to talk to at least one layperson about the technology you know and love. You might even be asked to present to a whole group of nonnuclear folks, perhaps as a pitch to some company tangential to your company’s business. So, without further ado, let me give you some pointers on the best way to approach this important and surprisingly complicated task.
Louis M. Shotkin
Nuclear Science and Engineering | Volume 35 | Number 2 | February 1969 | Pages 211-219
Technical Paper | doi.org/10.13182/NSE69-A21136
Articles are hosted by Taylor and Francis Online.
A general method is presented for determining the bounds on allowable disturbances, in linearly stable systems, for which the system remains asymptotically stable. It is based on transforming a set of nonlinear differential equations to a single equation that is valid within a given region of equilibrium. It is applicable to systems with a fairly general nonlinear feedback as well as to systems that exhibit finite escape time, thus extending previous methods. The physics enters through the linear characteristic roots, and provision is made for both real and complex roots. The method is also of use in determining the range of validity of space-independent reactor models. Applications are given to three examples of reactor systems, including the determination of reactor excursions.