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contributor authorF. Rienecker
contributor authorW. H. Moran
date accessioned2017-05-08T23:31:57Z
date available2017-05-08T23:31:57Z
date copyrightDecember, 1965
date issued1965
identifier issn0098-2202
identifier otherJFEGA4-27267#865_1.pdf
identifier urihttp://yetl.yabesh.ir/yetl/handle/yetl/106512
description abstractA large prompt-burst nuclear reactor, “Super Kukla,” required a core of material that would withstand unusually high stress levels resulting from rapid thermal expansion and inertia loads. An experimental investigation was undertaken to determine the properties of cast uranium—10 wt percent molybdenum alloy under static and dynamic conditions of loading at various temperatures for application in this reactor. Techniques were developed to cast, inspect by radiographic and ultrasonic means, machine, and nickel plate the material. Castings are in the form of rings, 30 in. OD, 18 in. ID, and 2 in. thick. Sound material with carbon content of less than 250 ppm was found to have a static yield strength of approximately 130,000 psi, ultimate strength of 133,000 psi, and elongation of 10 percent at room temperature. Sustained static loads of more than 40,000 psi in a normal atmosphere were found to induce a brittle fracture attributed to stress corrosion. Test specimens subjected to strain rates on the order of 20 in/in/sec withstood stresses of 200,000 psi in the gage region, but usually failed in the threaded ends.
publisherThe American Society of Mechanical Engineers (ASME)
titleUranium-Molybdenum Alloy for Use in a Prompt-Burst Reactor
typeJournal Paper
journal volume87
journal issue4
journal titleJournal of Fluids Engineering
identifier doi10.1115/1.3650831
journal fristpage865
journal lastpage870
identifier eissn1528-901X
keywordsAlloys
keywordsmolybdenum
keywordsUranium
keywordsStress
keywordsTemperature
keywordsNickel
keywordsMachinery
keywordsInertia (Mechanics)
keywordsThermal expansion
keywordsGages
keywordsSound
keywordsMolybdenum alloys
keywordsStress corrosion cracking
keywordsCarbon
keywordsElongation
keywordsBrittle fracture
keywordsNuclear reactors
keywordsYield strength AND Tensile strength
treeJournal of Fluids Engineering:;1965:;volume( 087 ):;issue: 004
contenttypeFulltext


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