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contributor authorJ. M. Steichen
contributor authorR. L. Knecht
date accessioned2017-05-08T23:01:41Z
date available2017-05-08T23:01:41Z
date copyrightMay, 1976
date issued1976
identifier issn0094-9930
identifier otherJPVTAS-28131#105_1.pdf
identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/89198
description abstractThe elevated temperature mechanical properties of large diameter (28 in.) seamless pipe produced by roll extrusion for use as primary piping for sodium coolant in the Fast Flux Test Facility (FFTF) have been characterized. The three heats of type 316H stainless steel piping material used in this study exhibited very consistent mechanical properties and chemical compositions. Tensile and creep-rupture properties exceed values on which the allowable stresses for ASME Code Case 1592 on Nuclear Components in Elevated Temperature Service were based. Tensile strength and ductility were essentially unchanged by aging in static sodium at 1050°F (566°C) for times to 10,000 hr. High strain rate tensile tests showed that tensile properties were insensitive to strain rate at temperatures to 900°F (482°C) and that for temperatures of 1050°F (566°C) and above both strength and ductility significantly increased with increasing strain rate. Fatigue-crack propagation properties were comparable to results obtained on plate material and no differences in crack propagation were found between axial and circumferential orientations.
publisherThe American Society of Mechanical Engineers (ASME)
titleMechanical Properties of Roll Extruded Nuclear Reactor Piping
typeJournal Paper
journal volume98
journal issue2
journal titleJournal of Pressure Vessel Technology
identifier doi10.1115/1.3454346
journal fristpage105
journal lastpage110
identifier eissn1528-8978
keywordsMechanical properties
keywordsPipes
keywordsNuclear reactors
keywordsTemperature
keywordsDuctility
keywordsSodium
keywordsStainless steel
keywordsTensile strength
keywordsTest facilities
keywordsASME Standards
keywordsCreep
keywordsRupture
keywordsExtruding
keywordsStress
keywordsCoolants
keywordsCrack propagation AND Fatigue cracks
treeJournal of Pressure Vessel Technology:;1976:;volume( 098 ):;issue: 002
contenttypeFulltext


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