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Application of Hastelloy X in gas-cooled reactor systems [electronic resource].

Published:
Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1976.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description:
Pages: 63 : digital, PDF file
Additional Creators:
Oak Ridge National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
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Summary:
Hastelloy X, an Ni--Cr--Fe--Mo alloy, may be an important structural alloy for components of gas-cooled reactor systems. Expected applications of this alloy in the High-Temperature Gas-Cooled Reactor (HTGR) are discussed, and the development of interim mechanical properties and supporting data are reported. Properties of concern include tensile, creep, creep-rupture, fatigue, creep-fatigue interaction, subcritical crack growth, thermal stability, and the influence of helium environments with controlled amounts of impurities on these properties. In order to develop these properties in helium environments that are expected to be prototypic of HTGR operating conditions, it was necessary to construct special environmental test systems. Details of construction and operating parameters are described. Interim results from tests designed to determine the above properties are presented. To date a fairly extensive amount of information has been generated on this material at Oak Ridge National Laboratory and elsewhere concerning behavior in air, which is reviewed. However, only limited data are available from tests conducted in helium. Comparisons of the fatigue and subcritical growth behavior in air between Hastelloy X and a number of other structural alloys are given.
Report Numbers:
E 1.99:ornl/tm-5405
ornl/tm-5405
Subject(s):
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Note:
Published through SciTech Connect.
10/01/1976.
"ornl/tm-5405"
DiStefano, J.R.; Rittenhouse, P.L.; Corwin, W.R.; Brinkman, C.R.; Strizak, J.P.; Lystrup, A.
Funding Information:
W-7405-ENG-26
View MARC record | catkey: 14463254