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
October 2025
Latest News
ITA to work with IAEA on advance geologic repository knowledge
The International Tunnelling and Underground Space Association (ITA), a nongovernmental organization made up of 81 member states working to advance the safe, beneficial use of subsurface spaces, is working with the International Atomic Energy Agency to support the advancement of geologic disposal facilities for high-level radioactive waste.
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.