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 8–12, 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
Nov 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
November 2025
Fusion Science and Technology
Latest News
PWR Corrosion Control in the Nuclear Industry
As many Pressurized Water Reactors (PWRs) approach or exceed 40 years of operation, maintaining asset integrity under aging infrastructure, tight outage schedules, and strict ALARA (As Low As Reasonably Achievable) mandates is a real challenge.
George J. Bohm
Nuclear Science and Engineering | Volume 22 | Number 2 | June 1965 | Pages 143-152
Technical Paper | doi.org/10.13182/NSE65-A20233
Articles are hosted by Taylor and Francis Online.
The transfer matrix method is used to determine the eigenvalues and eigenfunctions needed to obtain the response of nuclear power reactor internals to dynamic excitations. Transfer matrices and delta matrices are developed for a particular closed-cycle pressurized-water-reactor (PWR) configuration. Two cases are studied, 1) where the internals are rigidly supported near the bottom by the vessel walls and 2) where the vessel elastically supports the internals requiring that the combined structure be analyzed. The analysis takes into consideration structures with different cross sections and masses that are connected in series and/or parallel. Results obtained with a digital computer are shown. The method and the results obtained in this paper can be used for a complete reactor dynamical analysis of most PWR internals, since their structures are similar in design.