Zobrazeno 1 - 10
of 179
pro vyhledávání: '"J K, Wright"'
Autor:
Anubhav Sarmah, Raymond D. Mee, Kailash Arole, David Chi, Ethan M. Harkin, Smita Shivraj Dasari, Aniela J. K. Wright, Thang Q. Tran, Ankush Rout, Micah J. Green
Publikováno v:
Macromolecular Materials and Engineering, Vol 308, Iss 11, Pp n/a-n/a (2023)
Abstract This work shows that radio‐frequency (RF) fields can simultaneously align carbon nanotubes (CNTs) dispersed in a resin and induce Joule heating to cure the resin. The timescales of alignment and curing using RF heating are numerically comp
Externí odkaz:
https://doaj.org/article/6c7b1d7fc12247debcd4dd0738838d4d
Autor:
David H. Hurley, Amey Khanolkar, David S. Smith, R. E. Rupp, J. K. Wright, Stephen Reese, Richard N. Wright
Publikováno v:
Journal of Materials Engineering and Performance. 30:1513-1520
Non-contacting laser ultrasound is used to measure Young’s modulus, shear modulus, and Poisson’s ratio as functions of temperature for Alloys 617 and 709. These alloys are of interest for structural applications in advanced nuclear reactors. Desi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::97c7e8bba37c141110256cb4c91a10b0
https://doi.org/10.1007/s11665-020-05430-4
https://doi.org/10.1007/s11665-020-05430-4
Publikováno v:
Case Reports in Surgery, Vol 2015 (2015)
Iatrogenic perforation of the gallbladder during laparoscopic cholecystectomy is a well-known occurrence; however, the consequences of spillage of gallstones in the peritoneum and particularly intrathoracic complications are less defined. We describe
Externí odkaz:
https://doaj.org/article/6a4f261616b64984a42f1d9d97c834b9
Autor:
Ji-Yeon Park, Woo-Gon Kim, In-Jin Sah, Eung-Seon Kim, J. K. Wright, Richard N. Wright, T.M. Lillo, Min-Hwan Kim
Publikováno v:
Nuclear Engineering and Design. 329:142-146
The Ni-Cr-Mo-Co material Alloy 617 is the leading candidate for VHTR intermediate heat exchangers operating above 750 °C. Time-dependent properties are an important consideration in qualifying the alloy for construction of nuclear components. Creep
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2805855fc6e6e22a7a23717aad7daf12
https://doi.org/10.1016/j.nucengdes.2017.07.014
https://doi.org/10.1016/j.nucengdes.2017.07.014
Publikováno v:
Nuclear Engineering and Design. 322:331-335
Alloy 709 (UNS S31025) has shown enhanced performance, particularly in creep strength, over current generation high temperature structural materials, specifically Type 316 stainless steel and Grade 91. Accurate knowledge of the thermal properties of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0dac05434549f82efd9d7a7b88c9a288
https://doi.org/10.1016/j.nucengdes.2017.07.016
https://doi.org/10.1016/j.nucengdes.2017.07.016
Autor:
H. O'Dell, J. K. Wright, L. Gorden, Andrew Scanga, S. Karp, A. Rafferty, S. Alexopoulos, S. Geevarghese, L. Matsuoka, Joseph A. Awad, N. Schneider, R. Perri
Publikováno v:
Journal of Hepatology. 70:e565-e566
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3b6e47b82c12abaad75e8243e8d8deaf
https://doi.org/10.1016/s0618-8278(19)31127-2
https://doi.org/10.1016/s0618-8278(19)31127-2
Autor:
R. I. Jetter, Nancy J. Lybeck, T.-L. Sham, Robert W. Swindeman, J. K. Wright, Richard N. Wright
Publikováno v:
Volume 1B: Codes and Standards.
Alloy 617 (UNS N06617) 52Ni-22Cr-13Co-9Mo is the leading candidate material for the intermediate heat exchanger for the very high temperature reactor (VHTR). An ASME Task Group on Alloy 617 Qualification has drafted a Code Case for Alloy 617 to allow
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7b78f252b4f27deaa3a34c13cc54bd46
https://doi.org/10.1115/pvp2017-66069
https://doi.org/10.1115/pvp2017-66069
Publikováno v:
Metallurgical and Materials Transactions A. 45:3010-3022
Creep of Alloy 617, a solid solution Ni-Cr-Mo alloy, was studied in the temperature range of 1023 K to 1273 K (750 °C to 1000 °C). Typical power-law creep behavior with a stress exponent of approximately 5 is observed at temperatures from 1073 K to
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7c06de0b3b646147790b8aca34e3399e
https://doi.org/10.1007/s11661-014-2244-y
https://doi.org/10.1007/s11661-014-2244-y
Publikováno v:
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.
Alloy 617 is the leading candidate material for an intermediate heat exchanger for the very high temperature reactor (VHTR). As part of evaluating the behavior of this material in the expected service conditions, creep–fatigue testing was performed
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2363f89ded0c1fa5265d1b440e1f97ba
https://doi.org/10.1115/pvp2016-63704
https://doi.org/10.1115/pvp2016-63704