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Dive into the research topics where Jill K. Wright is active.

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Featured researches published by Jill K. Wright.


ASME 2013 Pressure Vessels and Piping Conference | 2013

Strain Rate Sensitivity of Alloys 800H and 617

Jill K. Wright; J.A. Simpson; Richard N. Wright; Laura Carroll; T. L. Sham

The flow stress of many materials is a function of the applied strain rate at elevated temperature. The magnitude of this effect is captured by the strain rate sensitivity parameter “m”. The strain rate sensitivity of two face–center cubic solid solution alloys that are proposed for use in high temperature heat exchanger or steam generator applications, Alloys 800H and 617, has been determined as a function of temperature over that range of temperatures relevant for these applications. In addition to determining the strain rate sensitivity, it is important for nuclear design within Section III of the ASME Boiler and Pressure Vessel Code to determine temperature below which the flow stress is not affected by the strain rate. This temperature has been determined for both Alloy 800H and Alloy 617. At high temperature the strain rate sensitivity of the two alloys is significant and they have similar m values. For Alloy 617 the temperature limit below which little or no strain rate sensitivity is observed is approximately 700°C. For Alloy 800H this temperature is approximately 650°C.Copyright


international conference on fuel cell science engineering and technology fuelcell collocated with asme international conference on energy sustainability | 2015

Effects of the Foil Centering on the Irradiation Performance of U10Mo Alloy Based Monolithic Mini-Plates

Jill K. Wright; Hakan Ozaltun

Monolithic plate-type fuel is a fuel form being developed for high performance research and test reactors to minimize the use of enriched material. These plate-type fuels consist of a high uranium density LEU foil contained within diffusion barriers and encapsulated within a cladding material. To benchmark this new design, effects of various geometrical and operational variables on irradiation performance have been evaluated. For this work, the effects of fuel foil centering on the thermo-mechanical performance of the mini-plates were studied. To evaluate these effects, a selected plate from RERTR-12 experiments, the Plate L1P756, was considered. The fuel foil was moved within the fuel plate to study the effects of the fuel centering on stress, strain and overall shape of the fuel elements. The thickness of the fuel foil, thickness of the Zr-liners and total thickness of the plate were held constant, except the centerline alignment of the fuel foil. For this, the position of the fuel foil was varied from the center position to a maximum offset corresponding to the minimum allowable aluminum cladding thickness of 0.1524 mm. Results for various offset cases were then compared to each other and to the ideal case of a centered fuel foil. Fabrication simulations indicated that the thermal expansion mismatch results in warping of the fuel plate during fabrication as the fuel plate is cooled from the HIP temperature when the fuel is not centered. Even if the model is constrained during cooling to simulate the rigid HIP can surrounding the fuel plate during cooling, warping is observed when the constraint is removed. Similarly, irradiation simulations revealed that the fuel offset causes virtually all irradiation-induced swelling to occur on the thin-cladding side of the plate. This is observed even for the smallest offset that was considered. The total magnitude of the swelling is approximately same for all offsets values.Copyright


Archive | 2013

Creep Rupture of Pressurized Alloy 617 Tubes

Jill K. Wright; Richard N. Wright

................................................................................................................................................ iv ACKNOWLEDGEMENTS .......................................................................................................................... v ACRONYMS ............................................................................................................................................... v


Nuclear Engineering and Design | 2012

CHARACTERIZATION OF ELEVATED TEMPERATURE PROPERTIES OF HEAT EXCHANGER AND STEAM GENERATOR ALLOYS

Jill K. Wright; Laura Carroll; C. Cabet; Thomas Lillo; Julian K. Benz; J.A. Simpson; W.R. Lloyd; J.A. Chapman; Richard N. Wright


Metallurgical and Materials Transactions A-physical Metallurgy and Materials Science | 2014

Threshold Stress Creep Behavior of Alloy 617 at Intermediate Temperatures

Julian K. Benz; Laura Carroll; Jill K. Wright; Richard N. Wright; Thomas Lillo


Comprehensive Nuclear Materials | 2012

Material Performance in Helium-Cooled Systems

Richard N. Wright; Jill K. Wright; C. Cabet


Volume 5: High-Pressure Technology; Rudy Scavuzzo Student Paper Symposium and 24th Annual Student Paper Competition; ASME Nondestructive Evaluation, Diagnosis and Prognosis Division (NDPD); Electric Power Research Institute (EPRI) Creep Fatigue Workshop | 2016

Determination of the Creep-Fatigue Interaction Diagram for Alloy 617

Jill K. Wright; Laura Carroll; T.-L. Sham; Nancy J. Lybeck; Richard N. Wright


Archive | 2014

Creep and Creep-Fatigue of Alloy 617 Weldments

Jill K. Wright; Laura Carroll; Richard N. Wright


Archive | 2013

Tensile Properties of Alloy 617 Bar Stock

Jill K. Wright; Richard N. Wright; Nancy Lybeck


Nuclear Engineering and Design | 2017

Creep and creep-rupture of Alloy 617

Jill K. Wright; Thomas Lillo; Richard N. Wright; Woo-Gon Kim; Injin Sah; Eung-Seon Kim; Ji-Yeon Park; Min-Hwan Kim

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Laura Carroll

Idaho National Laboratory

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Nancy J. Lybeck

Idaho National Laboratory

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Thomas Lillo

Idaho National Laboratory

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J.A. Simpson

Idaho National Laboratory

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Julian K. Benz

Idaho National Laboratory

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T.-L. Sham

Argonne National Laboratory

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C. Cabet

Idaho National Laboratory

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D.S. Smith

Idaho National Laboratory

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Hakan Ozaltun

Idaho National Laboratory

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