An improved methodology for determining tensile design strengths of Alloy 617

Kim, Woo‐Gon; Yin, Song-Nan; Park, Jiyeon; Hong, Sung-Deok

doi:10.1007/s12206-011-1024-5

Cited by 19 publications

(8 citation statements)

References 8 publications

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“…Sham et al suggested an alternate method for generating the design curves using the Huntington data set. Kim et al repeated the analysis using an expanded data set including data collected through world-wide literature surveys, manufacturing companies, and KAERI data [Kim, 2012]. In this paper, the alternate methodology was presented with minor modifications for a data set including data from Huntington, CEA, ORNL, and INL.…”

Section: Discussion Of Statistical Analysismentioning

confidence: 99%

Tensile Properties of Alloy 617 Bar Stock

Wright¹,

Wright²,

Lybeck³

2013

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Tensile testing has been conducted on Alloy 617 bar stock in the temperature range of room temperature -1000°C. Repeatability for replicate tests is excellent and temperature dependent properties are consistent with previous observations for this alloy. Comparability to historical data is significant since modern mill practice incorporates an additional refining step, electro-slag re-melting, that has only recently become standard practice.The results are compared to those of a reference plate that has been extensively characterized previously in this program. These tests provided data for an alternative heat and product form that is required for the ASME Boiler and Pressure Vessel Code qualification to allow this material to be used in nuclear pressure vessels. The results also extend the temperature range over which the alloy has been characterized compared to current allowable stresses in the ASME Code for non-nuclear pressure vessel design.The bar stock generally has higher strength and ductility than the reference plate. Statistical analysis has been performed on recent tensile data determined in this program grouped with CEA (Commissariat à l'énergie atomique et aux énergies alternatives -the French research organization) for contemporary plate material and Oak Ridge National Laboratory data from a number of years ago to determine if they are significantly different than data from the original draft code case data generated at Huntington Alloys many years ago. A best least-squares fit of a polynomial was used, although a piecewise function can provide a better fit for both the yield and tensile strength of the material as a function of temperature.Analysis of the yield strength data shows the 95% confidence bounds of the new data set overlaps that of the original data set over the entire temperature range, indicating no difference in the two data sets and very little change in the design curve. The 95% prediction bound for yield strength provides a consistent, meaningful lower bound for yield strength, and would be a good candidate for minimum yield strength at temperature.The 95% confidence bounds for the tensile strength of the new and old datasets do not overlap above about 625°C, indicating a difference between the data sets at higher temperatures. Including the additional newer data would cause minor changes in the average tensile strength design curve, resulting in a slightly more conservative curve. The 75% prediction bound for tensile strength provides a consistent, meaningful lower bound for average tensile strength, and would be a good candidate for average tensile strength at temperature. v vi CONTENTS

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Section: Discussion Of Statistical Analysismentioning

confidence: 99%

Tensile Properties of Alloy 617 Bar Stock

Wright¹,

Wright²,

Lybeck³

2013

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“…The slip evolution laws described in Eqs. (20) and (21) have been used to describe the hardening behavior of nickel-based alloys at different temperatures (see [35,6,24]). high-temperature fatigue and creep-fatigue loading (see Fig.…”

Section: Flow Rule and Evolution Equationsmentioning

confidence: 99%

“…with σ 0 0.2 and σ ∞ 0.2 estimated from Ref. [20], givingτ 0 = 268.2 MPa as a constant. This procedure has been previously employed to calibrate lattice friction stress [6].…”

Section: Model Parameter Calibrationmentioning

confidence: 99%

Polycrystal plasticity modeling of nickel-based superalloy IN 617 subjected to cyclic loading at high temperature

Zhang

Oskay

2016

Modelling Simul. Mater. Sci. Eng.

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A crystal plasticity finite element (CPFE) model considering isothermal, large deformation and cyclic loading conditions has been formulated and employed to investigate the mechanical response of a nickel-based alloy at high temperature. The investigations focus on fatigue and creep-fatigue hysteresis response of IN 617 subjected to fatigue and creep-fatigue cycles. A new slip resistance evolution equation is proposed to account for cyclic transient features induced by solute drag creep that occur in IN 617 at 950 • C. The crystal plasticity model parameters are calibrated against the experimental fatigue and creep-fatigue data based on an optimization procedure that relies on a surrogate modeling (i.e., Gaussian Process) technique to accelerate multi-parameter optimizations. The model predictions are validated against experimental data, which demonstrates the capability of the proposed model in capturing the hysteresis behavior for various hold times and strain ranges in the context of fatigue and creep-fatigue loading.

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“…Significant researches have been done to develop the next generation of nuclear reactors (Generation IV) [1][2][3]. Design of very high temperature reactor (VHTR) has been widely discussed by many researchers [4,5].…”

Section: Introductionmentioning

confidence: 99%

“…There are several structural components for this reactor system as the intermediate heat exchanger (IHX), hot gas ducts (HGD) and the reactor pressure vessel (RPV) that are exposed to very high temperatures. In order to achieve high efficiency, the coolant temperature at the outlet of the reactor is planned to be increased to 1000°C, which is 200°C and 450°C higher than in the other two Gen IV nuclear reactor candidates, Gas-Cooled Fast Reactor (GFC) and Supercritical Water Cooled Reactor [1]. During the running of the VHTR system, HGD and IHX structural materials may face many problems related to high temperature degradation of mechanical properties and especially acceleration of oxidation [6].…”

Section: Introductionmentioning

confidence: 99%