Tensile Properties of Alloy 617 Bar Stock

Technical Report · Mon Jul 01 04:00:00 EDT 2013

DOI:https://doi.org/10.2172/1097701· OSTI ID:1097701

Wright, Jill K. ^[1]; Lybeck, Nancy J. ^[1]; Wright, Richard N. ^[1]

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1. Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Alloy 617 is approved for non-nuclear construction in the ASME Boiler and Pressure Vessel Code Section I and Section VIII, Division 1 but is not currently qualified for nuclear use in ASME Code Section III. A draft Code Case was developed in the 1980’s to qualify the alloy for nuclear service but efforts were stopped before the approval process was completed. Renewed interest in high temperature nuclear reactors has resulted in a new effort to qualify Alloy 617 for use in nuclear pressure vessels. Tensile properties of the alloy are needed for several aspects of Code qualification. Minimum yield strength and average tensile strength at temperature are used to set time independent allowable stress, Sm, for structural materials in B&PV Code, Section III, Subsection NH. It must also be demonstrated that there is no minimum ductility between room temperatures and 427°C (the upper temperature limit for Subsection NB) to minimize the number of fatigue tests required for developing the fatigue design curve. The bar properties reported here represent data for an additional heat and product form. A forged and rolled plate, designated as a reference material for the program, has been studied extensively and tensile properties are presented for comparison. Both of the product forms that have been characterized in the current program, plate and bar, were produced using current mill practice that includes additional refining using electro-slag re-melting. This additional processing step was not used for some of the materials in the historical database and it is of interest to demonstrate that the properties of contemporary material are comparable to the historical values.

• Research Organization: Idaho National Laboratory (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 1097701
• Report Number(s): INL/EXT--13-29671
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
Alloy 617
High Temperature Materials
NGNP
Tensile Properties