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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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.
B. B. Chu, M. Mazumdar
Nuclear Science and Engineering | Volume 52 | Number 3 | November 1973 | Pages 396-398
Technical Note | doi.org/10.13182/NSE73-A19485
Articles are hosted by Taylor and Francis Online.
The method of correlated temperatures provided a technique for computing the hot channel factor when a maximum fixed, but nonzero, number of hot channels is permitted in a reactor core. This method made adequate allowance for the fact that, of the various identifiable uncertainties affecting the core, some are global and some are local in nature. In this Note, a method is provided which has the same objectives as those of the method of correlated temperatures and uses the same formulation, but does away with the Monte Carlo computations of the latter. It is believed that the analytical method provided in this Note can be more easily adapted to the computations of hot channel reliability in an actual reactor.
