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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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.
P. L. Arnsberger, M. Mazumdar
Nuclear Science and Engineering | Volume 47 | Number 1 | January 1972 | Pages 140-149
Technical paper | doi.org/10.13182/NSE72-A28427
Articles are hosted by Taylor and Francis Online.
In thermal hydraulic design of nuclear reactor cores it is of interest to know the probability for 0, 1, 2, . . D hot channels and/or cladding and fuel hot spots [i.e., channels (spots) in the core at which temperature limits are exceeded]. Furthermore, it might even be advantageous to design a core for a maximum permissible number of such hot channels (spots) by comparing the safety considerations with the plant efficiency. Numerical procedures available in the open literature using statistical methods are currently restricted to the evaluation of hot channel or hot spot factors corresponding to the requirement that either the most exposed nominal channel (spot) or all channels (spots) in the entire core do not exceed imposed temperature or heat flux limits. This paper describes a method, hereafter referred to as “Method of Correlated Temperatures,” which enables an evaluation to be made of the entire probability distribution of the number of hot channels as a function of the corresponding hot channel factor. A quantitative comparison is performed between the proposed method and other procedures currently in use by applying the different methods to a hot channel factor analysis of a simplified hypothetical LMFBR-type core.
