ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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!
Latest Magazine Issues
Oct 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
November 2025
Nuclear Technology
Fusion Science and Technology
Latest News
House, Senate bills aim to improve nuclear decommissioning and waste disposal
Two bills were introduced in the last several weeks aiming to address nuclear power at the end of life—decommissioning plants and recycling used fuel.
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.