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- W158847010 abstract "This report presents descriptions and results for seven of the eight in-reactor creepdown tests of Zircaloy fuel cladding. These tests, part of a joint program between the US NRC and Energieonderzoek Centrum Nederland, were conducted to study the behavior of Zircaloy fuel cladding under conditions that approximate those found in an operating pressurized-water power reactor. We present radial surface displacements as functions of time, average diametral or circumferential strains as a function of time, and isochronal deformation surfaces. These tests were conducted at 343/sup 0/C with external pressures from 13.3 to 18.7 MPa. Three of the specimens were subjected to stress reversal during their test runs, after which they were pressurized internally to pressures from 3.5 to 6.9 MPa. Fast flux (>1.0 MeV (0.16 pJ)) ranged from 3.8 x 10/sup 17/ to 5.0 x 10/sup 17/ n/(m/sup 2/.s). The most important conclusion to be drawn from this study involves the deformation of the cladding during testing. Contrary to similar tests conducted out of reactor, the in-reactor specimens did not deform uniformly, that is, by diametral contraction and smooth ovalization. Rather, the deformation surfaces were nonuniform - hills and valleys formed at irregular intervals. This implies that conventional concepts of creepmore » rate and simplified modeling procedures are insufficient for predicting cladding behavior. Sufficient data have been collected in this program to supply modelers with detailed, virtually hour by hour, descriptions of the cladding surface shapes. From these data new interpretations can be derived to predict cladding behavior.« less" @default.
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- W158847010 date "1981-03-01" @default.
- W158847010 modified "2023-09-26" @default.
- W158847010 title "Analyses of surface displacements of Zircaloy fuel cladding in the HOBBIE creepdown irradiation experiments" @default.
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