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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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New coolants, new fuels: A new generation of university reactors
Here’s an easy way to make aging U.S. power reactors look relatively youthful: Compare them (average age: 43) with the nation’s university research reactors. The 25 operating today have been licensed for an average of about 58 years.
James M. Kennedy, Ted B. Belytschko, Daniel F. Schoeberle
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 290-302
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32568
Articles are hosted by Taylor and Francis Online.
The STRAW code was developed for the analysis of core components subjected to high-pressure transients. It is a finite element code that models both the fluid and structures. The code is able to treat material nonlinearities and geometric nonlinearities due to large displacements. The fluid model uses a quasi-Eulerian element, which enables nodes to be moved independently. Time integration is by the explicit central difference method. Although the code was designed for the study of core mechanics, it is applicable to a wide variety of problems because it uses a finite element format. The STRAW calculations for a Stanford Research Institute cluster experiment show that reasonable predictions can be made of the maximum strains in the structures.