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contributor authorV. K. Sazawal
date accessioned2017-05-08T23:11:56Z
date available2017-05-08T23:11:56Z
date copyrightNovember, 1981
date issued1981
identifier issn0094-9930
identifier otherJPVTAS-28204#380_1.pdf
identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/95015
description abstractThis paper presents the results of a comprehensive trial application of the draft structural design criteria for highly irradiated core components to a typical blanket assembly duct. The development of the criteria (proposed RDT F 9-7) is sponsored by the U.S. Department of Energy. The activity focuses on the evaluation of the criteria using a typical breeder reactor blanket assembly as a test case and is not intended for judging the adequacy of the component design. Pertinent design rules from the draft criteria are applied to the component to determine: (a) difficulties, if any, that may arise in interpretation and application of the criteria, and (b) adequacy of the criteria rules and analysis methods to address various potential failure mechanisms expected in the reactor core during service. Based on the trial application, various recommendations are made to promote further development of the criteria.
publisherThe American Society of Mechanical Engineers (ASME)
titleTrial Application of the Draft Structural Design Criteria for Breeder Reactor Core Components to a Typical Blanket Assembly Duct
typeJournal Paper
journal volume103
journal issue4
journal titleJournal of Pressure Vessel Technology
identifier doi10.1115/1.3263417
journal fristpage380
journal lastpage387
identifier eissn1528-8978
keywordsStructural design
keywordsManufacturing
keywordsDucts
keywordsBreeder reactors
keywordsDesign AND Failure mechanisms
treeJournal of Pressure Vessel Technology:;1981:;volume( 103 ):;issue: 004
contenttypeFulltext


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