Jill K. Wright
Idaho National Laboratory
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Featured researches published by Jill K. Wright.
ASME 2013 Pressure Vessels and Piping Conference | 2013
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
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
Jill K. Wright; Richard N. Wright
................................................................................................................................................ iv ACKNOWLEDGEMENTS .......................................................................................................................... v ACRONYMS ............................................................................................................................................... v
Nuclear Engineering and Design | 2012
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
Julian K. Benz; Laura Carroll; Jill K. Wright; Richard N. Wright; Thomas Lillo
Comprehensive Nuclear Materials | 2012
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
Jill K. Wright; Laura Carroll; T.-L. Sham; Nancy J. Lybeck; Richard N. Wright
Archive | 2014
Jill K. Wright; Laura Carroll; Richard N. Wright
Archive | 2013
Jill K. Wright; Richard N. Wright; Nancy Lybeck
Nuclear Engineering and Design | 2017
Jill K. Wright; Thomas Lillo; Richard N. Wright; Woo-Gon Kim; Injin Sah; Eung-Seon Kim; Ji-Yeon Park; Min-Hwan Kim