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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Ariz. governor vetoes “fast track” bill for nuclear
Gov. Katie Hobbs put the brakes on legislation that would have eliminated some of Arizona’s regulations and oversight of small modular reactors, technology that is largely under consideration by data centers and heavy industrial power users.
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.