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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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.
E. Corran, C. A. Stapleton
Nuclear Science and Engineering | Volume 54 | Number 1 | May 1974 | Pages 47-54
Technical Paper | doi.org/10.13182/NSE74-A23392
Articles are hosted by Taylor and Francis Online.
A control system is described which will shut down a reactor in close to the minimum time that will allow subsequent restart on demand, despite fission product buildup. Errors in the reactor model, restrictions on operating conditions, and plant perturbations are taken into account. The system uses an on-line computer, requires no extra reactor instrumentation, and provides the operator at all times with an estimate of the minimum time to transfer the reactor from its current state to a suitable shutdown condition. During normal operating conditions, the operator may use the system to evaluate strategies satisfying various restart conditions. The results of simulation tests on the system are included.
