Zobrazeno 1 - 10
of 20
pro vyhledávání: '"Chan Hee CHO"'
Autor:
Chan Hee Cho, Bart G Pijls, John M Abrahams, Anne Roerink, Raissa Katembwe, Andrew Baker, Lucian B Solomon, Stuart A Callary
Publikováno v:
Acta Orthopaedica, Vol 94 (2023)
Background and purpose: We conducted a systematic review and meta-analysis of RSA studies to investigate the early and long-term migration patterns of acetabular cups and the influence of implant factors on cup migration over time. Methods: We perfor
Externí odkaz:
https://doaj.org/article/c2ce2049307f4e2b9d6e67e40946f664
Autor:
Sung Eun Kim, Myung Ho Lee, Chan Hee Cho, Jung-In Lee, Hyuk-Soo Han, Myung Chul Lee, Du Hyun Ro
Publikováno v:
Medicina, Vol 59, Iss 12, p 2104 (2023)
Background and Objectives: Stable fixation is essential for successful healing after medial open wedge high tibial osteotomy (MOWHTO) to minimize the risk of non-union and correction loss. In Asians, potential complications such as D-hole screw osteo
Externí odkaz:
https://doaj.org/article/19c17816feb44766823d1a2a1b94a08a
Publikováno v:
Knee Surgery, Sports Traumatology, Arthroscopy. 31:1123-1131
To investigate factors contributing to the de novo hyperextension after posterior cruciate ligament substituting (PS) total knee arthroplasty (TKA). Through a retrospective case–control study, de novo hyperextension patients were compared with pati
Publikováno v:
Knee surgery, sports traumatology, arthroscopy : official journal of the ESSKA.
To investigate factors contributing to the de novo hyperextension after posterior cruciate ligament substituting (PS) total knee arthroplasty (TKA).Through a retrospective case-control study, de novo hyperextension patients were compared with patient
Publikováno v:
Journal of the Korean Society for Nondestructive Testing. 35:258-267
Eddy current testing is widely used for inspecting steam generator tubing in nuclear power plants (NPPs). The inspection technique for steam generator tubing in NPPs should be qualified in accordance with examination guidelines. When the components o
Publikováno v:
Journal of the Korean Society for Nondestructive Testing. 34:254-259
A pressurized heavy water reactor (PHWR) core has 380 fuel channels contained and supported by a horizontal cylindrical vessel known as the calandria, whereas a pressurized water reactor (PWR) has only a single reactor vessel. The pressure tube, whic
Electrical Characteristics Measurement of Eddy Current Testing Instrument for Steam Generator in NPP
Publikováno v:
Journal of the Korean Society for Nondestructive Testing. 33:465-471
A steam generator in nuclear power plant is a heatexchager which is used to convert water into steam from heat produced in a nuclear reactor core, and the steam produced in steam generator is delivered to the turbine to generate electricity. Because
Publikováno v:
Journal of Mechanical Science and Technology. 27:679-683
The reliability and performance of steam generators (SGs) are serious concerns in the operation of nuclear power plants. In particular, SG tubing is subject to a variety of degradation processes that can lead to potential leakage or rupture. To preve
Publikováno v:
Journal of the Korean Society for Nondestructive Testing. 33:63-68
Some essential components in nuclear power plants are periodically inspected using non-destructive examinations, for example ultrasonic, eddy current and radiographic examinations, in order to determine their integrity. These components include nucle
Publikováno v:
OpenNano, Vol 12, Iss , Pp 100153- (2023)
Long acting injectables (LAIs) using polymeric microspheres has been developed to increase patient compliance and reduce side effects. Among many methods for manufacturing polymeric microspheres, microfluidics technology is known to have excellent ch
Externí odkaz:
https://doaj.org/article/9ebd73eec68a43b4a22d90c2efe19720