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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!
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Latest News
NNSA awards BWXT $1.5B defense fuels contract
The Department of Energy’s National Nuclear Security Administration has awarded BWX Technologies a contract valued at $1.5 billion to build a Domestic Uranium Enrichment Centrifuge Experiment (DUECE) pilot plant in Tennessee in support of the administration’s efforts to build out a domestic supply of unobligated enriched uranium for defense-related nuclear fuel.
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.