Hydride precipitation crack propagation in zircaloy cladding during a decreasing temperature history [electronic resource]

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Bibliographic Details
Online Access: Online Access (via OSTI)
Corporate Author: Lawrence Livermore National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C. : Oak Ridge, Tenn. : United States. Department of Energy ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 2000.
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MARC

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245 0 0 |a Hydride precipitation crack propagation in zircaloy cladding during a decreasing temperature history  |h [electronic resource] 
260 |a Washington, D.C. :  |b United States. Department of Energy ;  |a Oak Ridge, Tenn. :  |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,  |c 2000. 
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500 |a Track Nine Sessions, International Conference on Nuclear Engineering (ICONE), Nice (FR), 04/08/2001--04/12/2001. 
500 |a Stout, R B. 
520 3 |a An assessment of safety, design, and cost tradeoff issues for short (ten to fifty years) and longer (fifty to hundreds of years) interim dry storage of spent nuclear fuel in Zircaloy rods shall address potential failures of the Zircaloy cladding caused by the precipitation response of zirconium hydride platelets. If such assessment analyses are to be done rigorously, they will be necessarily complex because the precipitation response of zirconium hydride platelets is a stochastic functional of hydrogen concentration, temperature, stress, fabrication defect/texture structures, and flaw sizes of the cladding. Thus, there are, and probably always will be, zirhydride questions to analytically and experimentally resolve concerning the consistency, the completeness, and the certainty of models, data, the initial and the time-dependent boundary conditions. Some resolution of these questions will be required in order to have a defensible preference and tradeoffs decision analysis for assessing risks and consequences of the potential zirhydride induced cladding failures during dry storage time intervals. In the following brief discussion, one of these questions is posed as a consequence of an anomaly described in data reproducibility that was reported in the results of tests for hydrogen induced delayed cracking. The testing anomaly consisted of observing a significant differential in the measurable crack velocities (quasi-steady state at a prescribed load and temperature values) that depended on the approach direction, from above or from below, to the test temperature value. The testing method used was restricted to approaching a prescribed test temperature value from above. This anomaly illustrates the known thermodynamic non-equilibrium processes in the precipitation kinetics of zirhydride platelets that are dependent on temperature and stress histories. Detailed solubility limits of hydrogen in Zircaloy as a function of temperature, in terms of zirhydride precipitation and zirhydride dissolution solubility curves, were reported recently. In addition, other tests to evaluate the influence of an applied stress state on zirhydride precipitation kinetics have also been recently reported. 
536 |b W-7405-ENG-48. 
650 7 |a Boundary Conditions.  |2 local. 
650 7 |a Crack Propagation.  |2 local. 
650 7 |a Hydrides.  |2 local. 
650 7 |a Hydrogen.  |2 local. 
650 7 |a Kinetics.  |2 local. 
650 7 |a Dry Storage.  |2 local. 
650 7 |a Nuclear Engineering.  |2 local. 
650 7 |a Nuclear Fuels.  |2 local. 
650 7 |a Precipitation.  |2 local. 
650 7 |a Thermodynamics.  |2 local. 
650 7 |a Zircaloy.  |2 local. 
650 7 |a Zirconium Hydrides.  |2 local. 
650 7 |a Hydrogen.  |2 edbsc. 
650 7 |a Nuclear Fuel Cycle And Fuel Materials.  |2 edbsc. 
650 7 |a Materials Science.  |2 edbsc. 
650 7 |a Geosciences.  |2 edbsc. 
710 2 |a Lawrence Livermore National Laboratory.  |4 res. 
710 1 |a United States.  |b Department of Energy.  |4 spn. 
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