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Documenting the distribution, sources and fluxes of baseflow discharge into rivers is important for their management and for maintaining ecosystem health. This study uses major ion geochemistry, 222Rn, and 3H to differentiate between the input of low-salinity near-river waters (bank storage and return waters and/or interflow) and regional groundwater in an intermittent river from southeast Australia that is undergoing long-term changes in flow resulting from climate change. Baseflow discharge calculated by 222Rn mass balance was up to 1.3 m3/m/day in the high flow period in July 2019 and up to 0.1 m3/m/day at low flow conditions in November 2019. The distribution of 222Rn activities implies higher baseflow fluxes in the upper and middle reaches that have relatively steep topography and higher hydraulic gradients. The lower reaches received less baseflow due to subdued topography and fine-grained sediments. The observation that Cl concentrations did not increase uniformly downstream, however, implies that much of the baseflow may comprise bank return flow or interflow. This conclusion is also consistent with water mass balance calculations and the observation that 3H activities (1.85-3.00 TU) in the river were higher than in the groundwater (

Objectives To evaluate the diagnostic accuracy of the Xpert MTB/RIF assay for bone and joint tuberculosis (BJTB) using tissue specimens, and to compare the diagnostic accuracy of different types of tissue specimens. Methods This study involved 242 patients admitted with suspected BJTB between May 2018 and March 2020. The Xpert MTB/RIF assay was performed on surgically excised tissue. Diagnostic accuracy of the Xpert MTB/RIF assay was evaluated by culture, histopathology and a composite reference standard (CRS). Results One hundred and seventy-five patients were excluded (91 based on the exclusion criteria, and 84 as pus specimens were used instead of tissue specimens). Of the 67 patients enrolled, 14 were confirmed as BJTB, 20 as probable BJTB, 11 as possible BJTB, and 22 as non-BJTB. Using culture as the reference standard, sensitivity, specificity, positive predictive value (PPV), negative predictive value (NPV), positive likelihood ratio (PLR), negative likelihood ratio (NLR) and area under the curve (AUC) of the Xpert MTB/RIF assay were 92.9% (88.2–97.6%), 62.3% (56.1–68.5%), 39.4% (33.2–45.6%), 97.1% (92.3–100.0%), 2.464 (1.077–3.851), 0.114 (0.025–0.203) and 0.776 (0.654–0.897), respectively. When histopathology was used as the reference standard, the Xpert MTB/RIF assay had sensitivity, specificity, PPV, NPV, PLR, NLR and AUC of 79.3% (73.5–85.1%), 73.7% (67.8–79.6%), 69.7% (63.8–75.6%), 82.4% (76.5–88.3%), 3.015 (1.184–4.846), 0.281 (0.141–0.421) and 0.765 (0.646–0.884), respectively. Sensitivity, specificity, PPV, NPV, PLR, NLR and AUC obtained when using CRS as the reference were 73.3% (67.9–78.7%), 100.0% (100.0–100.0%), 100.0% (100.0–100.0%), 64.7% (58.5–70.9%), +∞, 0.267 (0.129–0.405) and 0.867 (0.781–0.952), respectively. Tissue samples were classified, and the positive rate of the Xpert MTB/RIF assay for BJTB using granulation tissue specimens was found to be significantly higher than that for caseous necrotic tissue, sequestrum and other necrotic connective tissues (P Conclusion The Xpert MTB/RIF assay showed high sensitivity and specificity for the diagnosis of BJTB from tissue specimens.

We propose a feature selection algorithm based on hybrid simulated annealing (SA) - genetic algorithm (GA) and random forests, whose procedure can be described as the following steps. First, set an initial temperature and create an initial solution as current solution by binary encoding of the features. Then, generate a new potential solution according to the principle of crossover and mutation in the genetic algorithm. Next, construct random forests and calculate the fitness degree of the new potential solution by using out-of-bag (OOB) error. The acceptance of new state is based on Metropolis criterion, and the steps are iterated until a predefined lowest temperature is reached. Finally, a contrast experiment has done to show that the hybrid algorithm we proposed has better classification and feature selection performance than the methods from the existing literature.

As solar cell back contact schemes have improved in recent years, the non-ideal emitter region has become a dominant contributor to overall losses in solar cell efficiency. Our analysis shows that these losses can be greatly reduced by creating a lightly ( 10 µm) is measured by cross-sectional etching and electron beam-induced current measurements. Electrochemical capacitance-voltage measurements are used to measure both the depth as well as the dopant profile resulting from the laser-driven process. We also analyse dislocation defects induced by the large thermal gradients inherent to the laser-based process which would greatly limit the device performance.

The Chinese Fusion Engineering Test Reactor (CFETR) is the next-generation fusion device of China for realization of fusion energy. Its mission aims to bridge the gaps between the International Thermonuclear Experimental Reactor and the demonstration reactor. To perform the maintenance work on the CFETR, remote handling systems shall be equipped on the device. To inspect and identify the status and position of the in-vessel components of CFETR, a remotely operated in-vessel viewing system (IVVS) shall be used. Such an IVVS prototype with articulated arm and viewing system has been built in China. Its dimension bases on the size of Experimental Advanced Superconducting Tokamak (EAST) due to similar shape of the reactor and the limited project budget. To assemble and store the IVVS around the Tokamak, a cylindrical vacuum vessel with foundation support inside is designed and checked. To isolate the vacuum of the vessel from the vacuum of Tokamak, an ultrahigh vacuum gate valve with a bellow is installed between them. To maintain the vacuum degree of the Tokamak after its connection with the vessel, a set of vacuum unit with molecular pump is configured for the vessel. Before integration testing on the EAST, some performance tests of the IVVS are carried out on the remote handling test facility and in other laboratories. The test results show that it is feasible to apply such an IVVS concept to the CFETR.

The steady state with duty cycle time 0.3–0.5 of Chinese fusion engineering testing reactor (CFETR) is a big challenge. To realize this goal, the divertor should be reliable. At the preconceptual phase of CFETR design, reliability engineering is engaged to determine how reliable of divertor is and how much level of reliability of divertor should be. The plasma facing components (PFCs), base plate, and support frame have been considered during the reliability analysis for the divertor modules. The relation of the reliability between a divertor system and its modules has been analyzed. The relations between steady-state operation with duty cycle time 0.3–0.5 and the reliability of divertor is studied in this paper. How the reliability of components, modules, and divertor system affects the duty cycle time of CFETR is also analyzed. To meet the requirement of duty cycle time, the lowest reliability level of divertor system is 0.3679 and its mean time to fail is only 1 year. The divertor system with such low reliability requires that each module should have a relative high reliability of 0.9794, and then, the PFCs should have higher reliability of 0.9930. These results are then must become the requirements for the engineering design of CFETR divertor in the future.

Experimental advanced superconducting tokamak (EAST) device is a D-shaped full superconducting tokamak with actively water cooled plasma-facing components. Before this upgrade, three generations divertors, which are steel divertor, carbon divertor, and international thermonuclear experimental reactor-like upper divertor, have been applied, respectively. To achieve long-pulse and high- $\beta $ H-mode plasma, new plasma configurations and shapes have been modeled and optimized in 2016 on EAST. The new geometry of lower divertor heavily relies on numerical simulations of the plasma in EAST. The new divertor is designed to fit the high- $\beta $ H-mode plasma and endure the heat flux up to 10 MW/m2. To achieve this goal, the lower carbon divertor will be replaced in EAST, which is now in conceptual design phase. Compared to the outer target side, the inner target side is prone to plasma detachment. First, the geometry and physics of the divertor should be better designed with the advanced physical operation mode. Second, the divertor should be in advanced geometry and high efficient cooling structure. Third, considering balance the detachment between inner target side and outer target side. This paper mainly introduces the research progress of the fourth-generation tungsten divertor in EAST.

This study aimed to improve polydimethylsiloxane (PDMS) conversion in the preparation of polycarbonate (PC)–polydimethylsiloxane (PDMS) copolymer through melt polycondensation. We examined the transesterification process of PDMS with diphenyl carbonate (DPC) and its copolymerization products with bisphenol-A (BPA) for different chain lengths of PDMS. The key factors affecting PDMS conversion were investigated. Results showed that long-chain PDMS required a higher critical transesterification level (38.6%) to improve miscibility with DPC. During polycondensation, side reactions were more prone to occur when the equilibrium transesterification level of long-chain PDMS was lower. PDMS conversion was also lower when more short-chain PDMS was fed. Increasing the chain length of PDMS also reduced PDMS conversion. Notably, increasing the amount of KOH can significantly improve PDMS conversion throughout the polycondensation stage by increasing the equilibrium transesterification level of long-chain PDMS, thereby inhibiting the occurrence of side reactions.

As a chronic metabolic disease, diabetes mellitus (DM) is broadly characterized by elevated levels of blood glucose. Novel epidemiological studies demonstrate that some diabetic patients have an increased risk of developing dementia compared with healthy individuals. Alzheimer’s disease (AD) is the most frequent cause of dementia and leads to major progressive deficits in memory and cognitive function. Multiple studies have identified an increased risk for AD in some diabetic populations, but it is still unclear which diabetic patients will develop dementia and which biological characteristics can predict cognitive decline. Although few mechanistic metabolic studies have shown clear pathophysiological links between DM and AD, there are several plausible ways this may occur. Since AD has many characteristics in common with impaired insulin signaling pathways, AD can be regarded as a metabolic disease. We conclude from the published literature that the body’s diabetic status under certain circumstances such as metabolic abnormalities can increase the incidence of AD by affecting glucose transport to the brain and reducing glucose metabolism. Furthermore, due to its plentiful lipid content and high energy requirement, the brain’s metabolism places great demands on mitochondria. Thus, the brain may be more susceptible to oxidative damage than the rest of the body. Emerging evidence suggests that both oxidative stress and mitochondrial dysfunction are related to amyloid-β (Aβ) pathology. Protein changes in the unfolded protein response or endoplasmic reticulum stress can regulate Aβ production and are closely associated with tau protein pathology. Altogether, metabolic disorders including glucose/lipid metabolism, oxidative stress, mitochondrial dysfunction, and protein changes caused by DM are associated with an impaired insulin signal pathway. These metabolic factors could increase the prevalence of AD in diabetic patients via the promotion of Aβ pathology.

We evaluated the application value of Xpert MTB/RIF and T-SPOT.TB in the diagnosis of bone and joint tuberculosis.One hundred two patients with suspected bone and joint tuberculosis (BJTB) were admitted to Zhengzhou Orthopaedics Hospital, Henan, China from April 2018 to February 2019. The Xpert MTB/RIF and T-SPOT.TB tests were performed using pus specimens and peripheral blood, respectively. The diagnostic performance of Xpert MTB/RIF and T-SPOT.TB tests was evaluated on the basis of the composite reference standard (CRS).A Total of 73 suspected BJTB were enrolled and categorized, including 12 confirmed BJTB, 27 probable BJTB and 34 non-BJTB. When CRS was used as the reference, the specificity, PPV and NLR values of the Xpert MTB/RIF assay were significantly higher than those of the T-SPOT.TB assay (97.1% vs. 82.4%, p 0.05; 96.7% vs. 85.4%, p 0.05; 0.26 vs. 0.12, p 0.05). However, the sensitivity, NPV and PLR values of the T-SPOT. TB assay were significantly higher than those of the Xpert MTB/RIF assay (89.7% vs. 74.4%, p 0.05; 87.5% vs. 76.7%, p 0.05; 5.08 vs. 2.52, p 0.05). The AUCs from Xpert MTB/RIF and T-SPOT. TB tests were 0.857 and 0.860, respectively. However, the difference was not statistically significant. The Xpert MTB/RIF and T-SPOT. TB tests demonstrated medium concordance in diagnosing BJTB.The sensitivity of T-SPOT.TB test combined with the specificity of Xpert MTB/RIF not only shorten the time of diagnosis but also improve the accuracy of diagnosis of BJTB and reduce the misdiagnosis rate. Therefore, they are useful for early diagnosis of BJTB.

Aeolian loess deposits contain abundant information about the evolution of the paleoenvironment. For example, paleoclimate changes recorded in Chinese loess area obtained significant achievement in the past few decades. Compared to Chinese loess, research on Indian loess is lacking. Currently, most studies focus on the Kashmir area located in the southern Himalayas, and studies on other areas are rare. However, field observations demonstrate that the sediments around the New Delhi-Agra-Jaipur Plain are similar to Chinese loess-paleosol sequences. For example, the boundary between two strata is transitional and without horizontal bedding. Moreover, obvious pedogenic horizons developed among sediment sequences, probably indicating unrecognised aeolian deposits in the Indo-Gangetic Plain (IGP). To confirm this, pilot samples were obtained from the IGP and detailed indoor measurements conducted. The results indicate that the distribution patterns of particle size and rare earth elements (REE) of the pilot samples are similar to Chinese loess. Furthermore, the scanning electronic microscopy (SEM) images of pilot samples show obvious conchoidal fractures, dash-shaped concavities, and abundant small pits that usually form through mechanical impact. These are typical characteristics of aeolian particles. In addition, environmental and rock magnetic measurements indicate that the dominant magnetic minerals in the pilot samples are magnetite and maghemite, and that they likely contain small amounts of hematite. Furthermore, conventional magnetic parameters are comparable with Chinese loess. Based on this, aeolian loess deposits are widely distributed in the IGP, which may have promoted the development of Indian farming and contributed towards the prosperity of ancient Indian civilisation. This study also provides a new and valuable record for the research on paleoclimate changes in the study area in the future.

Divertor is one of key components of tokamak fusion reactor. The CFETR is China Fusion Engineering Test Reactor. Its divertor will expose to tritium environment and neutron radiation. Materials of the divertor will be radioactived, and cannot be handled by personnel directly. To develop structure which compatible with robots handle for installation, maintenance and removing is required. This paper introduces a conceptual design of CFETR divertor module which compatible with remote handling end-effectors. The divertor module is confined by inner and outer support. The inner support is only confined divertor module radial, toroidal and vertical moving freedom degrees, but not confined rotating freedom degrees. The outer support is the structure that can confine rotating freedom degrees and should also be compatible with remote handling end-effectors.

The target box is designed to protect the body of divertor cassette. Every new EAST divertor cassette has two target boxes covering its body. The paper is about the structure design and optimizing scheme of the outer/inner tokamak divertor target box. The preliminary structure of target box is built up firstly. And the distribution of thermal load on the target boxes is discussed based on the theory and experiment results of plasma. Then some parameters of the target box’s structure, such as cooling tube radius, cooling water flow velocity and the length between two cooling tube, are selected to discuss the range of values’ limits. Based on the above results, a series of thermal simulations are made through changing the structure parameter values. Finally, using these simulation results the optimal design parameters set are found out.

In this work, trimesic acid was introduced in the preparation of cerium-manganese oxide, and its effect on thermal aging resistibility for catalytic diesel soot elimination was investigated systematically. The prepared catalysts were characterized by scanning electron microscopy (SEM), transmission electron microscopy (TEM), N2 adsorption–desorption, X-ray diffraction (XRD), Raman spectra, X-ray photoelectron spectroscopy (XPS) and H2-temperature programmed reduction (H2-TPR). The experimental results show that trimesic acid addition has no significant effect on the morphologies of cerium-manganese oxide catalyst, and also contribute litter to the suppression of catalyst particles sintering and textual features destroying. In addition, the crystal structure and high-temperature (800 °C) phase separation of CeO2-MnOx solid solution are not improved by the trimesic acid modification. But, noteworthily, trimesic acid assisted synthesis can obviously promote Mn4+ generation and keep up oxygen vacancy concentration and hence improve the product of highly active oxygen species (especially O 2 - ) of CeO2-MnOx catalyst during the thermal aging process. Furthermore, trimesic acid assistance can significantly alleviate the loss of CeO2-MnOx metal-support interaction caused by thermal aging, and maintain the ability to supply active oxygen at low-temperature (approximately 200–400 °C). Finally, after thermal aging at 800 °C for 12 h, the trimesic acid assisted synthesized CeO2-MnOx catalyst shows significantly better catalytic soot oxidation activity. Thus this work reveals that besides stabilizing textual and structural properties, stabilizing and optimizing electronic structure is another feasible pathway to enhance the thermal aging resistibility of CeO2-based soot oxidation catalysts.

An upgrade to the lower divertor is currently being planned for EAST superconducting tokamak, aiming at reaching over 400 s long-pulse H-mode operations with a full metal wall and a divertor heat load of ˜10 MW/m2. A new divertor concept for EAST, “Tightly Baffled Divertor”, suited to water- cooled W/Cu plasma face components (PFC) with minimized divertor volume, has been proposed to achieve Te,target

As a widely used classification integration algorithm, the random forests based on decision tree combination is mostly used for classification and regression problems, but its deficiencies still need to be improved. In this paper, we propose simulated annealing algorithm, and its parameters is combined with the global search optimal solution and local optimal solution to optimize search. Then, we propose a random forests hybrid algorithm by combining the Relief algorithm and annealing algorithm, briefly introduce its thoughts and algorithm flow, and also carry out simulation experiments. According to the experimental results, the classification effect of the hybrid algorithm is generally the best, which greatly improves the overall generalization performance of the random forests.

In-vessel components of the EAST superconducting tokamak upgraded from full carbon plasma facing material (PFM) to carbon PFM for upper and lower divertor, and molybdenum PFM for other surface in 2011. Carbon tiles were mechanical connected to CuCrZr heat sink can handle heat flux ∼3 MW/m2. EAST was planned to update plasma heating power to 36 MW. After that heat flux to divertor will be up to 10 MW/m2 for steady state operation and 15 MW/m2 for transient. Upgrading divertor accommodate high performance plasma operation requirement is necessary. Tungsten PFM with ITER-like monoblock and flat tungsten technology was developed for EAST upper divertor to handle the high heat flux. To meet tungsten divertor pumping requirement an in-vessel cryo-pump was designed to install in upper divertor area. Type-I edge localized mode (ELM) was observed during EAST plasma operation in 2012. Resonant Magnetic Perturbation (RMP) coils with ITER in vessel coils like insulation technology were developed for the ELM mitigation. Vertical Stability (VS) control coils are also upgrade to ITER-like insulation technology, and coils locations were optimized to obtain more effective instability control.

Chinese Academy of Sciences Institute of Plasma Physics (ASIPP) Experimental Advanced Superconducting Tokamak (EAST) has designed and built a new outer divertor with an ITER-like cooling system. As...

One of the most important research goals of EAST concerns long steady-state high-performance plasma pulse. It is a fusion engineering challenge for divertor to handle steady-state high heat flux form plasma. To accomplish this aim, full tungsten divertor has been designed for EAST to withstand high heat flux which is increasing rapidly. Full tungsten divertor is an ITER-like design which consists of monoblock units, end boxes and cassette body. The newest divertor of EAST will withstand more than 10 MW/m2 heat flux in target zone. The full tungsten divertor should be reliable during plasma discharge campaign to reduce the failure risk of plasma components under critical thermal power from plasma. Analysis and experiment results proved full tungsten divertor of EAST will be very reliable for future long steady-state high-performance plasma pulse. The design and application of full tungsten divertor of EAST can also bring experiences and answers for ITER or any next divertor fusion device on nuclear phase.

Mycoplasma pneumoniae is a major pathogen causing community-acquired pneumoniae (CAP), which is generally treated with macrolides. In recent years, however, although macrolide-resistant M. pneumoniae has been reported frequently, particularly in China, very little is known about the prevalence of macrolide-resistant M. pneumoniae infection in adults. In this study, we survey the macrolide-resistant M. pneumoniae in adults in Zhejiang province and characterize the mechanisms of resistance to macrolide. Six hundred fifty throat swab samples were collected from adult patients with CAP from January 2012 to August 2014. These samples were assayed by nested PCR and then cultivated for M. pneumoniae . All isolates were sequenced to determine the mutation in domain V of the 23S rRNA gene. The activities of 10 antibiotics against macrolide-resistant M. pneumoniae isolates were also investigated in vitro . Moreover, restriction fragment length polymorphism (RFLP) analysis of the amplified P1 gene was used to type 50 resistant strains. One hundred percent (71/71) of M. pneumoniae strains isolated from adults with CAP were resistant to erythromycin (MIC = 128 to >256 μg/ml), clarithromycin (MIC = 128 to >256 μg/ml), and azithromycin (MIC = 32 to >64 μg/ml). Furthermore, all macrolide-resistant M. pneumoniae strains identified had an A2063G mutation in domain V of the 23S rRNA gene. Forty-six resistant strains (92.0%) were classified into type I strain on the basis of P1 gene PCR-RFLP analysis. According to these findings, it is suggested that macrolide-resistant M. pneumoniae infection is very prevalence among adults in Zhejiang province. Thus, there is necessary to perform the epidemiological monitoring of macrolide-resistant M. pneumoniae in the future.

In the east updated divertor, some analyses have been done and the results show that the divertor body is safety. This article is about the analysis of divertor assembly parts. In the assembly parts of divertor the vacuum vessel (VV) is the permanent part and can’t be damaged, therefore a weak weld seam structure is designed to protect the important VV. In the same time a series of the finite element analysis has been done under the several loads such as electromagnetic loads and structure loads et al. The static finite element (FE) analysis result indicates that the assembly parts is strong enough to withstand the loads and the stress distribution is also satisfactory according to the design scheme. In the transient FE analysis the convergent stress value indicates that the dviertor assembly parts are safe under the worst case loads of disruption with the 1 MA plasmas current. Through a series of the FE simulation the maximum transient current that the divertor assembly parts can withstand is about 175 kA in the Fig. 8.

EAST, with full superconducting magnetic coils, has been designed and constructed to address the scientific and engineering issues under steady state operation. It has passive stabilizers with the function of protecting the vacuum vessel, heating systems and diagnostic components from the plasma particles and heat loads. As the vertical plasma motion is unstable in tokamak with elongated D-shape plasma, the passive stabilizers and in-vessel active feedback coils are used for vertical plasma position control in EAST. To accommodate with the new stage for high performance plasma and enhance the control of vertical stabilization in EAST, the project of passive stabilization loop (PSL), connect all the independent passive stabilizers together as a loop, has been accomplished. The PSL consists of 32 passive stabilizers and the current bridges. All the supporting structures of PSL are insulated from the vacuum vessel. The separate passive stabilizers are electrically connected together forming the upper and lower toroidal loops, and then the two loops are electrically connected by the copper current bridges. The current bridges are designed coaxial and symmetrical in order to counterpoise the electromagnetic forces. There are insulation layer and external resistor between the outer and inner bridges to avoid breakdown. What’s more, a stainless steel shell with graphite tiles is covered on the bridges to protect them from the plasma. The total resistance of PSL is reduced to 150 micro ohms by silver plating on the contact surface. As indicated, the PSL was fabricated and assembled successfully and met the design requirement for the plasma operation. With the PSL, the control of the vertical stabilization is improved.

CFETR is a fusion engineering test reactor. Its mission is to bridge the gaps between ITER and DEMO, and obtain the fusion energy power in China. However during the plasma operation the in-vessel components, plugs and other components of the CFETR would be influenced and activated by high energy neutrons, polluted by tritium. So the maintenance of these components must be handled in remote ways. First of all, the remote maintenance scheme should be planned to define how to do the maintenance work. Then the classification of the components must be performed to determine which component should be handled by remote ways. Finally the remote handling equipments should be configured to carry out the maintenance work to each component. Some R&D works have also been done on these remote handling equipments.

For the enclosure welding of the correction coil cases of CFETR, a electron beam welding equipment will be set up. The welding vacuum vessel is the requisite vacuum container for electron beam welding equipment. In the paper a large vessel is designed according to box-shaped shell theory. The preliminary structure parameters are achieved through the theory calculation. To improve the transport-ability, manufacture-ability and assembly-ability, the large vacuum vessel is divided into three segments. In course of structure design and analysis of the vessel, the 3D model of the phased vacuum vessel is established. And the weakest part of the vessel is chosen as analysis and optimized object. Through structure parameters optimizing and analysis simulation, the final required dimensions of the phased vacuum vessel is acquired, which sets up the solid basis for the successfully building of the electron beam welding equipment.

The scientific and the engineering missions of EAST are to explore the reactor related regimes with long pulse lengths and high plasma core confinement and solutions for power exhaust and particle control under steady state operation and to establish technology basis of full superconducting tokamaks. EAST can operate with double null or single null divertor mode. The goals of the divertor are to get high parameters plasma, long pulse operation and single or double null plasma shape. So the divertor is designed as up-down symmetry structure to provide large experimental flexibility. The divertor should have the capacity to endure higher heat flux and provide recycling and impurity control. Up to now, three generations divertors which are steel, carbon and tungsten divertor respectively have been developed and installed on EAST. The steel divertor is just used in the commissioning test of the host machine in 2006. The carbon divertor which is composed of graphite tiles, CuCrZr heat sink and stainless steel supports is commissioned to endure thermal load of no more than 4 MW/m2 in 2008. Thus the tungsten divertor which is based upon cassette and mono-block technology like ITER is expected to endure the heat flux up to 10 MW/m2 in 2014.

The neutron wall load ( \(P_{\mathrm{n}})\) of Chinese fusion engineering testing reactor (CFETR) will be less than 1 MW/m2. To meet the net tritium breeding ratio (TBR) of the reactor, a new water-cooled blanket concept is considered. The blanket neutronics schemes are performed to explore the local TBR issues in the \(P_{\mathrm{n}}\) range of 1–5 MW/m2, which aims at the effective design of the blanket concept considering the tritium self-sufficiency. As a result, the calculation results are compared with the local TBR values and the material fraction changes. It is found that the local TBR has the high value at low \(P_{\mathrm{n}}\) while the blanket size in radial direction is determined. It is mainly because of the total breeding area increasing due to the pipe pitch increasing in the model. This leads to the possibility for CFETR using a simplified blanket interior. In addition, to match the pressurized water reactor (PWR) water-cooled condition, a reduced size of blanket module in toroidal direction is achievable. It can be concluded that a PWR water-cooled blanket has more benefits to CFETR engineering implementation in the future.

For remote handling in a far distance and toxic substances leakage must be considered, International Thermonuclear Experimental Reactor has put forward higher requirement for the failure modes and reliability analysis of remote handling system. Based on the actual working condition of motor driving system when transfer cask remote handling the in-vessel components, all the failure modes of the motor driving system were analyzed and distinguished by software Isogragh, the main failure patterns and weak links were the control circuit failure mode, bearing failure mode, electrolytic capacitor and the insulation failure mode. Motor driving system reliability model in series was established, the reliability and mean time between failures were estimated by the component stress analysis method. The above-mentioned methods and results provide the basic references for the system reliability assessment, optimization design, making rapid and accurate judgment for potential failure when systems operating.

Availability analysis for Chinese fusion engineering testing reactor (CFETR) is very important at the pre-conceptual phase. Availability apportion are the theoretical basis of system design of CFETR. Availability analysis informs the development of the CFETR overall system and subsystem design. Availability analysis will enable the identification of key subsystems to achieve availability targets. The duty cycle of CFETR should be at least 0.3–0.5. Such design goals require all subsystems of CFETR must have a pretty high availability. The availability of CFETR can be defined by break time analysis results. Analysis results proved that the availability of CFETR is 0.5–0.7. All availability subsystems of CFETR can be apportioned from their relevant mean time before failure (MTBF) and mean time to repair (MTTR) data to meet the availability goals. The relation between reliability, maintainability and availability indicates that a subsystem could have a high availability though its reliability is pretty low. Availability apportionment and analysis indicate that the availability of blanket and divertor should be 0.769–0.91 to meet the design requirements and their availability can be improved by increase the MTBF and reduce the MTTR of blanket and divertor with the development of remote handling or remote maintenance technology for fusion reactor.

After EAST_2012 campaign, the updated divertor (upper part) has been designed and installed in EAST. The updated upper divertor is designed as cassette structure like ITER divertor. The structure analysis has been carried out for divertor cassette design in the worst case loads of disruption with the maximum 1 MA of the plasmas current. A series of finite elements analysis indicates that the divertor cassette is able to withstand the electromagnetic (EM) load resulting from halo current, combined with EM load caused by eddy current, gravity and pressure of cooling water.

A temperature control mechanism is presented for the nuclear material design of a breeding blanket module. It aims at exploring the acceptable material fractions maintaining the thermal balance inside a blanket module, which support the temperature requirement for tritium release and inventory. One-dimensional neutronics model is utilized to discuss the calculations. It is found that there is a mutual influence in the blanket interior by using the multi-layers structure. Firstly, the pure Li4SiO4 zones in the front area are the relative independent zones and have little thermal influence to other zones. The Beryllium zones only affect the adjacent zones, but the effect can be ignored. The second beryllium zone and the first mixed pebble zones are mainly limited to the reduced activation ferritic/martensitic material due to the lower temperature limitation. It indicates that the structural casing for nuclear materials should be reckoned in detail because of no cooling with it. It is confirmed that there is a temperature control methodology for the design of blanket nuclear materials using the linear variation of the temperature profile.

Experimental advanced superconducting tokamak device is a D-shaped full superconducting tokamak with actively water cooled plasma facing components. To achieve long pulse and high βH-mode plasma, new plasma position and shape are calculated and optimized during the campaign of 2013-2014. New divertors are designed and developed to fit the plasma and endure the heat flux up to 10 MW/m2. The divertor is International Thermonuclear Experimental Reactor-like. It bases on monoblock and cassette technology and is composed of plasma facing component (PFC) units, cassettes, and support systems. Monoblock structures are just employed on the PFC units of target plates of the divertors, thus W flat tiles are used on the baffles and dome. At the end of monoblocks, end boxes are applied. Cassettes act not only as the supports of the PFC units, but also as manifolds for the cooling channels of the units. The support systems consist of inner support rails, outer support rails, and auxiliary braces. The support systems are installed on the vacuum vessel before cassettes are put on. To dock the cassette with the support system, it is just lifted and pushed forward. To verify and optimize the structure, Research and Development work has carried out for the divertor. The prototypes of PFC units and cassettes are fabricated with different manufacture processes. The total assembly process is also simulated with these prototypes on mockup facility and the vacuum vessel. The results show that the divertor system can be manufactured successfully according to the requirements of drawings and installed conveniently and precisely on the tokamak. All these works certify that the design of the divertor is all right. The batch production of the divertors can be started.

To avoid the thermal damage induced by the neutral beam to the neck tube of Experimental Advanced Superconducting Tokamak equatorial port (A#), a thermal shielding (TS) is utilized to withstand the high heat load. For the TS, the cooling system is designed including the interface with outer main loop. Several layouts of the cooling circuits are compared before a determined option. In particular, thermal–hydraulic transportation of the cooling system is investigated using a large slenderness ratio mesh model. And a discrete method for heat loading is developed. It indicates that the heat affected zones are appearing in a center gathered distribution but scattering in the surrounding area. And the central heat affected zone assumes the peak heat flux on the surfaces of the Mo tiles. This is the dominant factor to the layout of cooling pipes due to the temperature limitation of the TS materials. As a result, a non-uniform layout for the cooling pipes in the heat sinks is obtained based on the computational fluid dynamic results.

An effective method for eddy current calculation has been developed for EAST’s new divertor by using ANSYS. A 3D model of a double null divertor for the EAST device was built to evaluate eddy currents and electromagnetic (EM) forces on these components. The main input to the model is the plasma current and poloidal field coil currents, which are loaded into the model using experimental data measured from the EAST discharges. These currents generate magnetic fields that match those producing an EAST discharge, and the time variation of these fields produces the eddy currents in the divertors, along with from the resulting EM forces. In addition, the first 10 time steps were discussed for the eddy current generation and changing trend. It indicates that a static analysis before a transient mode start can solve the eddy current origination in the initial time steps. With this method, the EM transient response of EAST’s new divertor can be predicted based on ANSYS simulations. Furthermore, the method is also an effective approach to estimate the EM results for the in-vessel components of a fusion reactor during a disruption.

In the ITER project the cryostat is one of the most important components. Cryostat shall transfer all the loads that derive from the TOKAMAK inner basic machine, and from the cryostat itself, to the floor of the TOKAMAK pit (during the normal and off-normal operational regimes, and at specified accidental conditions). This paper researches the dynamic structure strength of the ITER cryostat during the operation of TOKAMAK. Firstly the paper introduces the types of loads and the importance of every type load to the research. Then it gives out the method of building model and principle of simplified model, boundary conditions and the way of applying loads on the cryostat. Finally the author discussed the analysis result and the strength questions of cryostat, also, the author pointed out the opinions according to the analysis results.

Embedding virtual network requests in an underlying physical infrastructure, the so-called virtual network embedding (VNE) problem, has attracted significant research interests already. A realistic scenario might entail embedding multiple VN requests (MVNE) that arrive simultaneously (batch arrivals). The existing heuristic MVNE approaches neither consider the coordination among multiple VNR embeddings nor embed all the arriving VNRs simultaneously considering the available physical resources. This paper considers the MVNE problem in the scenario where the available physical resources may not be sufficient to satisfy the physical resource demands of all the VNRs in the batch. We explore applying genetic algorithm (GA) to handle the MVNE problem. We propose an algorithm to decide which VNRs could be mapped together. Extensive simulations are carried out to evaluate the performance of the proposed algorithms in terms of the VN acceptance ratio and the long-term revenue of the service provider.

We have developed an all-laser processing technique by means of two industrially-relevant continuous-wave fiber lasers operating at 1070 nm. This approach is capable of both substrate heating with a large defocused beam and material processing with a second scanned beam, and is suitable for a variety of photovoltaic applications. We have demonstrated this technique for rapid crystallization of thin film (~10 μm) silicon on glass, which is a low cost alternative to wafer-based solar cells. We have also applied this technique to wafer silicon to control dopant diffusion at the surface region where the focused line beam rapidly melts the substrate that then regrows epitaxially. Finite element simulations have been used to model the melt depth as a function of preheat temperature and line beam power. This process is carried out in tens of seconds for an area approximately 10 cm 2 using only about 1 kW of total optical power and is readily scalable. In this paper, we will discuss our results with both c-Si wafers and thin-film silicon.

The passive stabilization loop (PSL) is part of the plasma stabilization system built in the EAST. Its purpose is to provide passive feedback control of the plasma vertical instability on short time scales. To accommodate with the new stage for high performance plasma and enhance the control of vertical stabilization in EAST, the project of PSL has been carried out. The eddy currents are induced by the vertical displacement events (VDEs) and disruption. The distribution of the eddy currents depend on the structure of the PSL and the formation of the induction. The global model is created and meshed by the ANSYS software. Based on the simulation of plasma VDEs and disruption, the distribution and decay curve of the eddy currents on the PSL are obtained. The stress and the strain caused by the eddy currents and the magnetic field are calculated. To decrease the resistance of the joint and enhance anti-corrosion of the joint surface, the silvered craft is used. In the experiment of test model, the resistance is decreased to half after silvered with the same matrix material and under the same preload. The PSL is insulated from the vacuum vessel at the supports of passive stabilizers. The insulation structure is designed and tested with ceramic material. The PSL is designed, fabricated and assembled with the total resistance 150 μΩ. It can supply passive feedback control to the plasma by the eddy currents induced by the VDEs, which could enhance the vertical placement control of plasma.

On EAST Tokamak, DC glow discharge (GDC) is developed to clean the first wall of plasma. It can effectively control the recycling of H, C, O impurities and improve the wall conditions. There are four GDCs which distribute equally on the EAST Tokamak vacuum vessel wall. Each GDC is equipped with an anode, a stainless steel cover and four support legs. The anode is insulated from cover with Al2O3 ceramics. After a round of experiment, the value of insulation resistance of GDC decreases remarkably due to metallization. To protect the insulation parts and heighten the reliability, ceramic protection covers are used on the GDCs. The other measures which can heighten insulation grades are also taken. After upgrade, the insulation resistance of each GDC between anode and ground is raised highly. When the pressure reaches 4 Pa, H2-GDC and He-GDC is strarted. Boronation and siliconization are also applied to the device wall conditioning. After GDC cleaning, the impurities and partial pressure of remainder gases in vacuum vessel (VV) is decreased greatly and vacuum degree of VV can reach high easily.

The first wall in Experimental Advanced Superconducting Tokamak (EAST) has used many graphite tiles to face the plasma. All graphite ties have been mounted on heat sink using screw bolts which had been preloaded to produce clamp force. The clamp force is very important to keep the graphite tiles on the surface of the heat sink tightly because the heat flux will cross this contacting surface in a small thermal resistor. Without the clamp force the small gap between graphite tiles and heat sink will lead thermal power cannot be carried away by cooling water. The worse is some bolts turned out with the loss of clamp force. From the mathematical models the process of the loss of clamp force has been studied. Research results explain how the different thermal expansion of three members of the screw joint leads to the clamp force decrease to zero under temperature rise and external force and how the stiffness affect the relationship between the clamp force and temperature. The research also gets the critical temperature point that the clamp force can remain above zero. Research results indicated this screw joint is absolute to lose their clamp force during the EAST running so that the bolt joints should be redesign to improve its reliability.

EAST plasma facing components (PFCs) have the function of protecting the vacuum vessel, heating systems and diagnostic components from the plasma particles and heat loads, and also additional to this particles and heat loads handling. The PFCs are designed up–down symmetry to accommodate with both double null and single null plasma configuration. All PFCs use graphite tile for plasma facing surfaces affixed to copper alloy heat sink considering economical factor. Based on this structural design, detailed structural and thermal analysis had been carried out. A special deep hole drilling technology was developed to drill cooling channels directly on heat sink for high efficient heat removal. A dry lubricate material is used between stainless steel support and heat sink for the purpose of absorption of thermal expansion. And analysis results show that the present PFCs need to be improved for the next stage of steady state operation. The PFCs are installed in the vacuum vessel together with in-vessel coils, cryopump and diagnostic components. The design, analysis, manufacture and assembly have been finished. As indicated, all the in-vessel components were fabricated and assembled successfully and meet the design requirement for the plasma operation.

In this work, we demonstrated a simple method to test the point contact design and determine the Surface Recombination Velocity (SRV) of the point contact solar cells from a single PL image. The thermally grown silicon dioxide is patterned by using lithographic means. The size, pitch and pattern of the point contact opening holes are varied in order to find the relationship between opening density and the effective carrier lifetime of the entire cell region. The advantages of this new characterization method compare with other SRV test methods are first, it is simple, reliable and fast, requires no other equipment but only a single PL image; second, a large quantity of design can be tested on a same wafer simultaneously.

To identify the specific antigens of the fifth stage larvae (larvae V) of Angiostrongylus cantonensis in soluble proteins.The techniques of two-dimensional electrophoresis (2-DE) and immunoblot were employed to analyze the soluble components of larvae V antigens. The resulting protein spots were identified by mass spectrometry and the specific antigen and immunogenic peptide segment profiles determined.Larvae V was identified by immunoblot of peptide immune murine sera.Immunoblot of 2-DE showed that there were 8 specific antigen spots in females and 4 in males of larvae V. The 12 protein spots had a pH range of 5-7 and a molecular weight of 24-40 kD. Among 12 spot, actin-1 and galectin-1 were identified successfully. And a peptide (NH2-KNGDIALHFNPRFDEK) was predicted as epitope and synthesized. The binding capacity of murine immune sera could identify the 32 000 of larvae V.Galectin and actin are common antigens of female and male larvae V of A.cantonensis. And a peptide from galectin-1 may become a potential target for immunologic diagnosis and immunological mediator.

Introduction: Mycoplasma pneumoniae ( M. pneumoniae ) is the most common atypical pathogen that causes respiratory infections in humans. Laboratory tests are important in the diagnosis of M. pneumoniae because of the atypical features in clinical signs and symptoms. Nowadays, both the P1 adhesin gene and 16S ribosomal (r) RNA (rRNA) gene of M. pneumoniae have been widely detected by polymerase chain reaction (PCR). The purpose of the present study was to evaluate the most suitable target in the detection of M. pneumonia via nested PCR . Methodology: Both the P1 adhesin gene and 16S rRNA gene for nested PCR reaction conditions were optimized through an orthogonal test and single-factor experiment. Then, the sensitivity of the two sets of targets was evaluated. Finally, based on the optimal conditions, 55 clinical samples of throat swabs collected from adult patients in 2013 were examined by established nested PCR. Result: The results revealed that PCR detection of the 16S rRNA gene was more sensitive than the P1 adhesin gene because the detection limits for both the P1 gene and 16S rRNA gene were at least 100 fg and 10 fg of M. pneumoniae DNA, respectively. Furthermore, the positive rate for detection of the 16S rRNA gene (30/55; 54.5%) was higher than that of the P1 adhesin gene (25/55; 45.5%). Conclusion: Our results indicate that the 16S rRNA gene is more suitable for diagnosis of M. pneumoniae infection than the P1 adhesin gene due to its higher sensitivity and positive rate in clinical samples.

EAST tokamak is one of the advanced full superconducting tokamaks in the world. To achieve better plasma parameters, new plasma position and shape are calculated and optimized in the 2013's update. New divertors should be deigned and developed to endure higher heat flux less than 10MW/m2. The divertor is ITER-like structure. It bases on mono-block and cassette technology. The divertor is composed of PFC units, cassettes and support systems. Mono-block structures are just employed on the PFC units of target plates of the divertors, thus W flat tiles are used on the baffles and dome. Cassettes act as not only the supports of the PFC units, but also the cooling channels of the units. The support systems consist of inner support rails, outer support rails and auxiliary braces. The systems are installed on vacuum vessel before cassettes putting on. When cassette assembly with support system, it is just lifted and pushed forward. To optimize and verify the structure, R&D work has done on the divertor. The prototypes of PFC units in different positions and cassettes with different manufacture processes are fabricated. The assembly process is also simulated with these prototypes on mimic facility and vacuum vessel. The results show that the divertor system can be manufactured successfully according to the drawing requirements. And they can also be installed conveniently and precisely on the tokamak. All R&D work and tests will certify that the design of divertor is all right.

This paper presents the design and implementation a voltage controlled oscillator (VCO) and injection locked frequency divider (ILFD) special for the Ka-band frequency synthesizer in 130-nm CMOS technology. The VCO core consists of a NMOS-only cross-coupled pair for negative resistance generation and a varactor for frequency tuning. The ILFD is based on hybrid differential injection technique with combining the tail-and the direct injectors. The simulated frequency tuning range (FTR) of the VCO increases from 26.6GHz to 28.2GHz as the tuning voltage increases from 0 to 1.2V. Post simulation shows the VCO and ILFD achieved the phase noise of −97.2dBc/Hz and −103.2dBc/Hz respectively at 1MHz offset. The VCO and ILFD consume 12 mW and 4 mW of power respectively from 1.2V supply voltage.

A high speed and wide range CML frequency divider was realized in 130nm CMOS by using the capacitive degeneration technique. Varactors are placed at the source of the cross-coupled transistors to improve the self-oscillation frequency of dividers. With the tuning of varactors and PMOS load, wide range can be realized. When working at 1.2V supply voltage, a maximum locking range of 16.9 GHz, from the incident frequency 0.3 to 17.2 GHz, is achieved at the incident power of 0 dBm. The frequency divider consumes a static current of 3.6 mA.