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RISS 인기검색어
- 검색키워드
- 저자 : Yatsuka, K. (검색결과 5 건)
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Unexpected Complications and Safe Management in Laparoscopic Pancreaticoduodenectomy
Yuichi Nagakawa,Yatsuka Sahara,Yuichi Hosokawa,Chie Takishita,Tetsushi Nakajima,Yousuke Hijikata,Kazuhiko Kasuya,Kenji Katsumata,Akihiko Tsuchida Korean Society of Gastrointestinal Cancer 2017 Journal of digestive cancer reports Vol.5 No.1
Although laparoscopic pancreaticoduodenectomy (LPD) is considered as minimally invasive surgery, an advanced level of laparoscopic skill is still required. LPD comprises various procedures including reconstruction. Therefore, establishment of a safe approach at each step is needed. Prevention of intraoperative bleeding is the most important factor in safe completion of LPD. The establishment of effective retraction methods is also important at each site to prevent vascular injury. I also recommend the "uncinate process first" approach during initial cases of LPD, in which the branches of the inferior pancreaticoduodenal artery are dissected first, at points where they enter the uncinate process. This approach is performed at the left side of the superior mesenteric artery (SMA) before isolating the pancreatic head from the right aspect of the SMA, which allows safe dissection without bleeding. Safe and reliable reconstruction is also important to prevent postoperative complications. Laparoscopic pancreatojejunostomy requires highly skilled suturing technique. Pancreatojejunostomy through a small abdominal incision, as in hybrid-LPD, facilitates reconstruction. In LPD, the surgical view is limited. Therefore, we must carefully verify the position of the pancreaticobiliary limb. A twisted mesentery may cause severe congestion of the pancreaticobiliary limb following reconstruction, resulting in severe complications. We must secure the appropriate position of the pancreaticobiliary limb before starting reconstruction. We describe the incidence of intraoperative and postoperative complications and appropriate technique for safe performance of LPD.
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Sohn, S.H.,Lim, J.H.,Yim, S.W.,Hyun, O.B.,Kim, H.R.,Yatsuka, K.,Isojima, S.,Masuda, T.,Watanabe, M.,Ryoo, H.S.,Yang, H.S.,Kim, D.L.,Hwang, S.D. Institute of Electrical and Electronics Engineers 2007 IEEE transactions on applied superconductivity Vol.17 No.2
<P>As high temperature superconducting (HTS) power cables have some merits over conventional cables, several demonstration projects on the HTS cable system are presently under way around the world. Korea Electric Power Corporation (KEPCO) also initiated an HTS cable project in 2002 with the Korean government's support. A three phase 100 m HTS cable system with a capacity of 50 MVA has been installed at Gochang test yard, located in Chonnbuk province, Korea. The HTS cable system is composed of a 100 m-long cable, two terminations and a cooling system. The rated current is 1,250 A<SUB>rms</SUB> and the rated voltage is 22.9 kV considering compatibility with the conventional power distribution system in Korea. Main purposes of this project are to verify the performance of an HTS cable system and to evaluate the potential of the HTS cable system from the viewpoint of power utilities. The real grid application of the HTS cable system requires the demonstration of system reliability, accumulated operation experiences, and it has to meet the practical needs of the utilities. In such a meaning, this project provides various challenges for KEPCO, and the feedback will be delivered to cable manufacturers. This user initiative test will facilitate the introduction of HTS cable systems into a real grid network. The installation process of the HTS cable system and some results of the preliminary test were presented in this paper.</P>
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Vorpahl, Christian,Alekseev, Andrey,Arshad, Shakeib,Hatae, Takaki,Khodak, Andrei,Klabacha, Jonathan,Le Guern, Frederic,Mukhin, Eugene,Pak, Sunil,Seon, Changrae,Smith, Mark,Yatsuka, Eiichi,Zvonkov, Ale North-Holland 2017 Fusion engineering and design Vol.123 No.-
<P><B>Abstract</B></P> <P>Numerous plasma-near mirrors of optical diagnostics in ITER require protection from erosion and deposition caused by impinging particles. This is achieved by 63 Diagnostic Shutters, which shall operate in vacuum under high thermal and neutron fluxes over 20 years without maintenance, ruling out standard engineering solutions. In fact, these conditions are unprecedented even on fusion devices. Hence, qualification R&D efforts are extensive, because if a shutter fails, so does the respective diagnostic.</P> <P>Shutter design tasks are widespread among Domestic Agencies and their suppliers, because every shutter is part of the diagnostic it shall protect when not in use. However, as these highly resembling systems have obvious synergy potential, a coordination strategy for all ITER shutters was implemented at IO.</P> <P>An extensive shutter experience collection including failure reports from 14 fusion devices was performed. These are summarized in the present work. For the first time, the state-of-the-art of shutters is thereby defined and assessed as to its applicability to ITER. Furthermore, design-driving environmental effects due to the specific operating conditions are recalled and evaluated. The findings of both assessments are put into context with the current designs of all ITER shutters. In a next step, these are reviewed with emphasis on synergies between different shutter systems. Finally, recommendations on necessary prototyping and generic components are given.</P> <P><B>Highlights</B></P> <P> <UL> <LI> Plasma-near first mirrors of ITER optical diagnostics are protected by 63 so-called <I>Diagnostic Shutters.</I> </LI> <LI> Harsh conditions rule out standard engineering solutions. </LI> <LI> If a shutter fails, so does its diagnostic, impeding ITER operation. </LI> <LI> As a design starting point, the state-of-the-art was defined by an extensive experience collection, the most frequent causes of failure being increased friction, standard mechanical problems and operational loads. </LI> <LI> All current ITER shutter designs were reviewed, yielding a limited set of <I>critical</I> components: Actuators, bearings and vacuum feedthroughs. </LI> <LI> Consequent recommendations for necessary R&D in an integrated strategy for all shutters are presented. </LI> </UL> </P>
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Edge profile measurements using Thomson scattering on the KSTAR tokamak.
Lee, J H,Oh, S,Lee, W R,Ko, W H,Kim, K P,Lee, K D,Jeon, Y M,Yoon, S W,Cho, K W,Narihara, K,Yamada, I,Yasuhara, R,Hatae, T,Yatsuka, E,Ono, T,Hong, J H American Institute of Physics 2014 Review of scientific instruments Vol.85 No.11
<P>In the KSTAR Tokamak, a 'Tangential Thomson Scattering' (TTS) diagnostic system has been designed and installed to measure electron density and temperature profiles. In the edge system, TTS has 12 optical fiber bundles to measure the edge profiles with 10-15 mm spatial resolution. These 12 optical fibers and their spatial resolution are not enough to measure the pedestal width with a high accuracy but allow observations of L-H transition or H-L transitions at the edge. For these measurements, the prototype ITER edge Thomson Nd:YAG laser system manufactured by JAEA in Japan is installed. In this paper, the KSTAR TTS system is briefly described and some TTS edge profiles are presented and compared against the KSTAR Charge Exchange Spectroscopy and other diagnostics. The future upgrade plan of the system is also discussed in this paper.</P>
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