Schardt, J. Flow-induced vibration for light water reactors. Progress report, December 1976--May 1977. United States: N. p., 1977.
Web. doi:10.2172/5217268.
Schardt, J. Flow-induced vibration for light water reactors. Progress report, December 1976--May 1977. United States. doi:10.2172/5217268.
Schardt, J. Thu .
"Flow-induced vibration for light water reactors. Progress report, December 1976--May 1977". United States.
doi:10.2172/5217268. https://www.osti.gov/servlets/purl/5217268.
@article{osti_5217268,
title = {Flow-induced vibration for light water reactors. Progress report, December 1976--May 1977},
author = {Schardt, J.},
abstractNote = {The report describes the program objectives, overall work plans, and progress achieved. A description is also given of the related state-of-the-art flow-induced vibration (FIV) technology which represents the starting point of the program. The program has been developed to increase plant availability through substantially reducing downtime caused by FIV failure of components. It is a four-year balanced effort of fundamental studies, analyses, tests of idealized conditions, and realistic tests of reactor components, all leading to the preparation of design guides and criteria for LWR's. The specific goals of the program are to: (1) produce improved FIV design criteria; (2) provide improved analytical methods for predicting behavior of components; (3) provide general scaling laws which will improve the accuracy of reduced-scale tests (required for those situations where it is impossible to predict the FIV response analytically or through full-scale testing); and (4) identify high FIV risk areas. To achieve these goals, the program has been divided into four major tasks: (1) fundamental studies; (2) model and full-size tests; (3) design methods, guides and criteria; and (4) program administration. Task 1 will provide a better understanding of FIV phenomena through a combination of fundamental tests and analyses of geometries common in LWR's and mechanisms which can cause FIV. The studies will systematically vary parameters using relatively small-scale idealized geometries and controlled flow fields. Task 2 will verify and extend the results of Task 1 through the testing of realistic LWR component geometries. Task 3 will develop analytical methods, as well as utilize the results of Tasks 1 and 2 to produce design guides, predictive models, and scaling laws. Task 4 will administrate the program, as well as insure that pressure water reactor (PWR) needs are given proper consideration.},
doi = {10.2172/5217268},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Sep 01 00:00:00 EDT 1977},
month = {Thu Sep 01 00:00:00 EDT 1977}
}
