Changing Models for Commercialization and Implementation of Biocontrol in the Developing and the Developed World

Photodynamic therapy (PDT) is a non-invasive, selective, and cost-effective cancer therapy. The development of readily accessible templates that allow rapid structural modification for further improvement of PDT remains important. We previously reported thiophene-based organic D-π-A sensitizers consisted of an electron-donating (D) moiety, a π-conjugated bridge (π) moiety, and an electron-accepting (A) moiety as valuable templates for a photosensitizer that can be used in PDT. Our preliminary structure-activity relationship study revealed that the structure of the A moiety significantly influences its phototoxicity. In this study, we evaluated the photoabsorptive, cellular uptake, and photo-oxidizing abilities of D-π-A sensitizers that contained different A moieties. The level of phototoxicity of the D-π-A sensitizers was rationalized by considering those three abilities. In addition, we observed the ability of amphiphilic sensitizers containing either a carboxylic acid or an amide in an A moiety to form aggregates that penetrate cells mainly via endocytosis

Toward the Cross-Institutional Data Integration From Shibboleth Federated LMS

Through this study, we aim to examine a method for data integration in shared Learning Management System (LMS) in authentication federation. We proposed a method of transmitting ePTID and learning data with user’s consent as a method for data integration across institutions. The method is compared with the other existing methods to realize the shared LMS. We discuss the suitable method for next version of GakuNinMoodle and conclude that our requirements are not fully satisfied by a single method

Optimal Intravascular Ultrasound-Guided Percutaneous Coronary Intervention in Patients With Multivessel Disease

BACKGROUND: Intravascular ultrasound (IVUS) was only rarely used in landmark trials comparing percutaneous coronary intervention (PCI) with coronary artery bypass grafting (CABG) in patients with multivessel disease. OBJECTIVES: The authors aimed to evaluate clinical outcomes after optimal IVUS-guided PCI in patients undergoing multivessel PCI. METHODS: The OPTIVUS (OPTimal IntraVascular UltraSound)-Complex PCI study multivessel cohort was a prospective multicenter single-arm study enrolling 1, 021 patients undergoing multivessel PCI, including left anterior descending coronary artery using IVUS, aiming to meet the prespecified criteria (OPTIVUS criteria: minimum stent area > distal reference lumen area [stent length ≥28mm], and minimum stent area >0.8 × average reference lumen area [stent length <28mm]) for optimal stent expansion. The primary endpoint was major adverse cardiac and cerebrovascular events (MACCE) (death/myocardial infarction/stroke/any coronary revascularization). The predefined performance goals were derived from the CREDO-Kyoto (Coronary REvascularization Demonstrating Outcome study in Kyoto) PCI/CABG registry cohort-2 fulfilling the inclusion criteria in this study. RESULTS: In this study, 40.1% of the patients met OPTIVUS criteria in all stented lesions. The cumulative 1-year incidence of the primary endpoint was 10.3% (95% CI: 8.4%-12.2%), which was significantly lower than the predefined PCI performance goal of 27.5% (P < 0.001), and which was numerically lower than the predefined CABG performance goal of 13.8%. The cumulative 1-year incidence of the primary endpoint was not significantly different regardless of meeting or not meeting OPTIVUS criteria. CONCLUSIONS: Contemporary PCI practice conducted in the OPTIVUS-Complex PCI study multivessel cohort was associated with a significantly lower MACCE rate than the predefined PCI performance goal, and with a numerically lower MACCE rate than the predefined CABG performance goal at 1 year

Conceptual design of the MGI system for JT-60SA

Disruption mitigation is of high priority for future tokamaks like ITER and DEMO. Massive gas injection (MGI) has proven to be an effective method in medium size machines and will likely be part of future disruption mitigation systems. For further research, the large superconducting tokamak JT-60SA will be equipped with a MGI system as an experimental equipment. This system will consist of two in-vessel MGI valves, which are mounted in opposite segments of the machine, vacuum feed throughs, a gas preparation system and an industrial PLC for control. The MGI valves are a scaled version of the spring-driven valve used in ADSEX Upgrade with an internal gas reservoir of 815 cm³, a maximum mitigation gas pressure of 6.5 MPa, a closing pressure of about 2 MPa, a nozzle diameter of 28 mm and an opening time below 2 ms. CFD simulations with common gas mixtures indicate a peak flow rate of 3.8 kg/s after 1.6 ms. The valve has a size of 140 mm x 110 mm x 292 mm. The gas preparation system allows easy and reproducible mixing of two gases by using an electronic pressure controller

Design of stabilizing plate of JT-60SA

The stabilizing plate of JT-60SA which is the largest superconducting tokamak, has been designed based on an electromagnetic and structural analysis. The stabilizing plate plays a role of both a passive stabilizer of magnetohydrodynamics (MHD) instabilities such as vertical displacement event (VDE) and resistive wall mode, and the first wall at low field side in combination with carbon tiles. The stabilizing plate is made of SS316L with low cobalt content and has double skin structure with 10mm thickness each in order to have simultaneously high resistivity in the toroidal direction and high strength against plasma disruption as well as seismic events. A finite element method for the calculation of the electromagnetic force induced by disruption and structural analysis has been applied. The most serious event whichis fast (~4 ms) major disruption, is considered. The eddy current reaches up to 100 MA/m2, which induces electromagnetic force < 120 MN/m3. The distribution of eddy current in the stabilizing plate is determined by openings (ports) for diagnostics and heating which cause separation and combination of the eddy current. The stabilizing plate has been modified in order to satisfy allowable membrane, bend and peak stress of SS316L. Trial manufacture of a part of the stabilizing plate has been done to investigate the effect of weld on the deformationof the stabilizing plate resulting from the contraction of the weld metal. We have chosen how to weld, e.g. amount of welding, groove shape of each metallic plate consisting of the stabilizing plate to minimize the deformation and maximize the allowable stress. The arrangement of heat sinks and coolant pipes, and carbon tiles has also been done, taking into account the long pulse operation of JT-60SA.31st Symposium of Fusion Technology (SOFT2020

Design of stabilizing plate of JT-60SA

The stabilizing plate (SP) of JT-60SA has been designed based on an electromagnetic and a structural analysis. The SP plays a role of both a passive stabilizer of magnetohydrodynamics (MHD) instability and a first wall at low field side in combination with a graphite tile. The SP has a double skin structure with 10 mm thickness each in order to have simultaneously high resistivity in the toroidal direction and high strength against plasma disruption as well as a seismic event. A finite element method for the calculation of the electromagnetic force induced by disruption and the structural analysis has been applied. The most serious event which is fast major disruption, is mainly considered. The eddy current reaches up to 100 MA/m2, which induces electromagnetic force <120 MN/m3. The SP has been modified in order to satisfy the allowable membrane, bend and peak stress of SS316 L. Trial manufacture of a part of the SP has been done to investigate the effect of the weld on the deformation of the SP resulting from the contraction of the weld metal. The arrangement of heat sinks and coolant pipes, and graphite tiles has also been done, taking into account the long pulse operation of the JT-60SA plasma. 1. Introduction The project of JT-60SA [1] is in progress at Naka, Japan, as a satellite tokamak in the Broader Approach activity under the international collaboration between Japan and Europa. The JT-60SA tokamak, which is the largest superconducting device, was successfully completed in March 2020 and is in the commissioning phase, which is planned by May 2021, including the first plasma initiation. The purpose of JT-60SA is a demonstration and study of the steady-state plasma with high beta targeting on the supplement to ITER toward DEMO and contributing to optimizing ITER operation scenarios. After the commissioning phase, we will upgrade the JT-60SA tokamak for 26 months. We will install many in-vessel components such as in-vessel coils, lower divertor, a cooling system including a heat-sink for in-vessel walls, the stabilizing plate (SP), and additional heating systems. The SP plays a role of both a passive stabilizer of magnetohydrodynamics (MHD) instabilities such as vertical displacement event (VDE) and resistive wall mode (RWM), and the first wall at low field side in combination with a heat-sink as well as a graphite tile. The in-vessel metal wall whose purpose is the stabilization of MHD instabilities is installed in some tokamaks such as NSTX [2], KSTAR [3], EAST [4]. The principle of stabilization of MHD instabilities by the in-vessel metal wall is that eddy current induced by MHD instabilities produces a magnetic field that pushes plasma back and stabilizes MHD instabilities. The in-vessel metal wall named passive stabilizer plate surrounds the upper and lower region of the plasma at a low field side in tokamaks except for JT-60SA. The in-vessel metal wall called stabilizing plate in JT-60SA surrounds the whole region of plasma at the low field side to obtain the steady-state high beta plasma. Fig. 1 shows the bird’s eye view of the SP as well as a part of the vacuum vessel (VV), error field correction coil (EFCC), fast positioning control coil (FPCC), and resistive wall mode coil (RWMC) of JT-60SA. The SP can be toroidally separated into 18 sections and connected to the vacuum vessel by 74 pedestals which are equipped with 18 support frames. Fig. 2 shows the poloidal cross-section of the SP, the VV, lower and upper divertors in combination with the flux surface of the double- null divertor configuration of the JT-60SA plasma. The plasma does not attach but gets closer to the SP within a distance of 10 mm for effective MHD stabilization. The specification of the SP is listed in the Table 1. The material of the SP is stainless steel 316 L with low cobalt content (Co <0.05 wt%) to avoid the production of cobalt-60 which is a radioactive isotope and can be produced by the fission reaction with neutrons during deuterium-deuterium experiments. Fig. 3 shows the exploded view of one toroidal section of the SP. The SP consists of the main part of the SP as shown in Fig. 3a) and the support frame having * Corresponding author. E-mail address: [email protected] (S. Yamamoto). Contents lists available at ScienceDirect Fusion Engineering and Design journal homepage: www.elsevier.com/locate/fusengdes https://doi.org/10.1016/j.fusengdes.2021.112361 Received 30 November 2020; Received in revised form 1 February 2021; Accepted 15 February 202