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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.
G. Blaesser, J. A. Larrimore
Nuclear Science and Engineering | Volume 37 | Number 2 | August 1969 | Pages 186-191
Technical Paper | doi.org/10.13182/NSE69-A20677
Articles are hosted by Taylor and Francis Online.
A discrete neutron kinetics for periodically pulsed fast reactors is formulated in which the time behavior of the delayed neutron precursor concentrations is considered explicitly only just before and just after each power pulse. The power pulse is represented by a delta function and a general integration of the precursor equations between pulses is used. The difference equations obtained are well suited for use in digital simulation of pulsed reactors. An “inhour equation” for pulsed reactors is derived from the difference equations and is shown to reduce to the relation obtained from the period-averaged kinetics equations, if the deviation from pulsed criticality is small.
