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AbstractAbstract
[en] The Small-Scale Clad Effects Study of the HSST Program was initiated to study the interaction of stainless cladding with flaws initiated in and propagating in base metal. From the designer's viewpoint stainless cladding is primarily viewed as a corrosion- and crud-prevention measure in light-water reactor vessel design, and except for its effect upon fatigue in thermal transients, its effect upon structural integrity has heretofore been largely disregarded. With the more recent focus of safety studies upon LOCA scenarios that emphasize the behavior of small flaws, it has become evident that stainless cladding may have a key role in the propagation and/or arrest of propagating flaws. A complicating factor in understanding the role of stainless cladding in this setting is its fracture toughness as a function of radiation dose and as a function of fabrication process for which meager data exist. The initial phase of this study has attempted to address this question by testing stainless-clad specimens that had been subjected to heat treatments to simulate beginning-of-life and end-of-life toughness conditions to fast-running cracks
Original Title
PWR; BWR
Primary Subject
Secondary Subject
Source
1982; 11 p; 10. water reactor safety research information conference; Gaithersburg, MD (USA); 12 - 15 Oct 1982; Available from NTIS, PC A02/MF A01 as DE83001926
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ACCIDENTS, ALLOYS, CARBON ADDITIONS, CARBON STEELS, CHROMIUM ALLOYS, CONTAINERS, CORROSION RESISTANT ALLOYS, IRON ALLOYS, IRON BASE ALLOYS, JOINTS, MATERIALS, MECHANICAL PROPERTIES, RADIATION EFFECTS, REACTOR ACCIDENTS, REACTORS, STEELS, STRESSES, TRANSITION ELEMENT ALLOYS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue