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Previous studies showed that coat color significantly affects hair cortisol levels but not serum cortisol and serotonin levels in heifers and dairy cows under heat stress conditions. As a follow-up study, we tested whether both serum and hair cortisol and serotonin levels in winter-housed dairy cows were affected by coat color (black vs white). Twenty multiparous high-yielding dairy cows (DIM = 110 ± 25, milk yield = 35 ± 2.1 kg) were assigned to one of the following groups: 1) black coat color (BCC; over 85% of coat black, n = 14) and 2) white coat color (WCC; over 85% of coat white, n = 6). The experimental period lasted 60 d (from December to February), during which the animals were kept in a building with free stalls that had dry river sand bedding. Blood was harvested for 3 consecutive days at the end of the study. Hair was harvested from the forehead of each individual at the beginning and on the end-day of the study. Cortisol and serotonin hormones were measured in serum and hair. Data were analyzed using t-test. The results revealed that cows with BCC had lower hair cortisol and higher hair serotonin levels than those with WCC (P0.05). No differences in serum cortisol levels were observed between cows with WCC and BCC (P0.05). The serum serotonin level was lower in cows with WCC compared to the BCC group (P0.05). Taken together, coat color significantly affected stress levels indicated by higher hair cortisol and lower hair serotonin levels in WCC cows in addition to lower serum serotonin levels in the corresponding animals. This feature of coat color should be considered as a management tool, particularly in countries with long winters.

In April 2020, manufacturing of the ITER vacuum vessel (VV) first sector has been completed by the Korean domestic agency, manufacturing having started in February 2012. The ITER VV sector is the largest fusion VV structure in the world. Each step of the manufacturing was a challenge as a first-of-a-kind, and a French nuclear pressure vessel. The paper provides an overview of the major challenges which were overcome over the last 10 years.

Customized cosmetics immediately made on the spot are now in the market. The present study surveyed 1084 consumers to obtain general insights into their perceptions and perspectives on this novel type of cosmetic. Over half of the total respondents (57.2%) answered they were likely to purchase customized cosmetics; however, a large proportion of consumers also thought microbiological (59.2%)/chemical safety (69.4%) of cosmetics were not good. This reflects consumer anxiety regarding safety issues concerning the customized cosmetics. Even customized cosmetics are regulated by the cosmetic act in each country (i.e., the Cosmetic Act in the Republic of Korea, the Federal Food, Drug, and Cosmetic Act in the USA, and EC Cosmetic Regulation 1123/2009 in Europe), there have been no specific regulations for customized cosmetics made on the spot worldwide so far. To dispel consumer concerns and establish a principled market for the new cosmetics in the field, proper management plans should be established based on consumer surveys. This study indicated that consumers thought it was important to manage the facility/equipment and safety of raw materials (19.7%, each). We believe this study provides a valuable resource for understanding consumers’ perceptions and requirements on customized cosmetics, which contributes to establishing future regulations and guidelines.

ITER has many ports to install various diagnostics which view and measure various plasma parameters. One of the ports, the upper port #18 (UP18) is designed to integrate three tenant diagnostic systems: vacuum ultraviolet spectrometer, neutron activation system, and upper vertical neutron camera. The key design drivers for the port integration are requirements on neutron shielding and maintenance. In this paper, we discuss the neutron shielding design made following the as low as reasonable achievable principle in order to reduce the shut-down dose rate in the interspace and port cell which are human-accessible areas. The design choice for radiation shielding of electronics in the port cell is also discussed. The port maintenance in ITER consists of remote handling operation for the port plug and manual (or assisted-manual) operation for the interspace and port cell areas. The compatibility with the ITER maintenance strategy is investigated for UP18 and the associated issues are addressed.

Manufacturing design of Korean sectors and ports for the ITER Vacuum Vessel (VV) has been developed to comply with the tight tolerance and severe inspection requirements. The first VV sector and lower ports are being fabricated slowly under strict regulations after verification using several real scale mock-ups and qualifications for welding, forming and NDE. During three years after start of fabrication, manufacturing progress on four poloidal segments of the first sector is that (1) all inner shells were welded, (2) forgings for complicate components have been machined, (3) port stubs and poloidal T-ribs were assembled, and (4) machined components are welded on the inner shells by narrow-gap TIG welding and electron beam welding. The progress of lower ports is that (1) inner shells of stub extensions were bent and treated with heat, (2) T-ribs were fabricated and examined by qualified phased array UT, (3) supporting pads and gussets have been machined, and (4) inner shells are assembled with T-ribs and machined forgings. The progress rate of manufacturing is around 40% up to the end of 2015 for the first sector and lower port stub extensions.

Manufacturing design has been developed by Hyundai Heavy Industries Co., Ltd. (HHI) and Korea Domestic Agency (KODA) to manufacture real product. As the first step of development of the manufacturing design, fabrication feasibility study was carried out in accordance with the RCC-MR 2007. Fabrication sequence was drafted and engineering analyses have been performed to guarantee structural integrity of manufacturing design and to minimize welding distortion. Several design modification proposals were derived during fabrication feasibility study. Fabrication sequence and manufacturing techniques have been established based on the results of a fabrication feasibility study. 3D multi-part model was developed based on the reference multi-body model and manufacturing drawings have been produced. A full scale mock-up of the lower port stub extension (PSE) has been fabricated in order to verify weldability, applicability of non-destructive examination (NDE) and welding distortion. Several qualifications were also conducted to confirm that the manufacturing design satisfies the requirements for bending, solution heat treatment, welding and NDE. Manufacturing and inspection plans (MIP) have been prepared to start real fabrication. In this paper, manufacturing design procedure and major technical results of manufacturing design development are presented for ITER VV lower port.

To improve the plasma vertical stabilization during tokamak operation, partial pure copper layer could be considered on the inner shell of vacuum vessel which is large complex component made of stainless steel. The copper cladding has been a great challenge due to the complicated configuration and difficulty of dissimilar metal joining. From an engineering point of view, there are several candidates for the copper cladding such as cold spray, overlay welding and explosive welding. In this paper, fabrication feasibility study for copper cladding has been carried out by using cold spray method, and a set of full scale mock-up of in-vessel component has been conducted to demonstrate applicability of copper cold spray and to verify copper layer. The results of copper cold spray on test specimens and mock-up showed good properties and no defects on the thick copper layer. Optimum conditions of copper cold spray have been developed based on these results. Accordingly, it can be concluded that cold spray is a feasible and practical method to achieve thick copper cladding on tokamak component.

A neutron activation system (NAS) measures neutron fluence at the first wall and the total neutron flux from plasma, providing the fusion power evaluation. A pneumatic transfer method is conventionally utilized to transfer encapsulated activation samples between the irradiation stations and counting station. The temperature of the irradiation station, near the first wall could reach too high for the conventional polymer-based materials, such as polyethylene, to be used as a capsule material for the ITER NAS. Considering the environment of the irradiation station of the ITER NAS, the candidate capsule materials are chosen as four materials: RAFM (reduced activation ferritic martensitic) steel, SiCf/SiC composite, tungsten, and CFC (carbon fiber-reinforced carbon). Preliminary investigation reveals that the CFC is the most promising capsule material for ITER NAS due to its good thermal and magnetic properties as well as low activation by neutron irradiation. Various kinds of mock-up capsules are fabricated using CFC with the consideration of the volume of inner space accommodating activation samples. Preliminary pneumatic transfer experiments carried out in the small-scale test-bed suggest that the transfer speed of capsule should be slower than 10 m/s and the wall thickness of the capsule should be thicker than 2 mm so as not to be broken by impact damage. The present study shows the feasibility of using CFC as a capsule material for the ITER NAS.

The main objective of ITER tritium Storage and Delivery System (SDS) is contracted to develop an optimal metal hydride bed that can be reveal the unprecedented fueling performance for the Tokamak. One function of the hydride bed is to keep safety requirements in terms of confinement of tritium. The hydride material for storing the deuterium and tritium fuelling gases is being made narrow with depleted uranium (DU) by its good performance. DU also has its own uncertainties, however, in applying it to realize the getter bed system having an all-round capability, especially in aspect of safety. This paper deals with from bed design target to the design variables in terms of comparison of risk-based multi-criteria using HAZOP (risk matrix) analysis. In analysis of the risks, important variables that denotes safety-effective, or cost-effective, or maintainability-effective, or manufacturability-effective are sometimes mutually interrelated with each other. As a conclusion the authors could recommend the way to concentrate and minimize the bed design variables with most meaningful risk-containing components that can be applied to increase the performance of hydride bed. It needs, however, that further study of comparison of risk analyses should be proceeded to complete the hydride bed design.

The reliable monitoring of the position of an encapsulated activation sample is essential to ensure the diagnostic accuracy and the maintenance of the ITER neutron activation system (NAS). Conventional methods using optical or electrical detectors to determine the capsule position is difficult to be used in the ITER NAS because of limited space as well as extremely high electromagnetic and radiation environment. In this study, new methods using the flow rate change inside a transfer tube assembly and the propagation characteristics of sound wave are investigated for the reliable determination of the capsule position. Experimental results confirm that the abrupt reduction of flow rate in the transfer tube assembly provides information for the final position of the capsule with a high spatial resolution less than 1 mm. The variation of flow rate is also found to indicate the operational status of the pneumatic transfer system. In the case of capsule lost accident, a laboratory scale test has demonstrated that the exact position of the lost capsule can be determined by the sound wave method in which the time delay between an incident sound signal and a reflected one by the capsule is measured so as to provide the position of the capsule with a spatial resolution of 0.2 m. These two capsule position monitoring methods are expected to improve the accuracy, operational stability, and the ability to handle the accident in the ITER NAS.

Thermal shield (TS) is to be installed in ITER tokamak to minimize radiation heat load transferring from the vacuum vessel and the cryostat to the superconducting magnet operating at 4.5 K. The TS shall be properly designed so that the radiation heat load is below the specified requirement for the magnet. This paper describes how the ITER TS is modeled to verify its thermal performance. The 3D finite element (FE) models of repetitive sections of the whole TS were developed in this study. The major geometric simplifications applied to the FE models are illustrated. Passively cooled removable panel on the cryostat TS (CTS) for the in-cryostat maintenance of the magnet was modeled considering thermal contact at the joint. The boundary temperature of the CTS support was determined from the analysis of cryostat with the TS. Total heat load from the TS to the magnet was evaluated for the steady state of plasma operation. Cool-down behavior of the TS was also investigated by the transient analysis of the representative models. The maximum panel temperature and the helium outlet temperature were obtained during cool-down of TS.

The diagnostic upper port plug in ITER is a long metal box cantilevered to the vacuum vessel port with 42 × M52 studs and nuts. The plug structure has a heavy payload at the front, such as the diagnostic first wall and the diagnostic shield module to protect the diagnostic components from plasma and neutron fluxes. This kind of structural configuration is susceptible to a resonance with the transient external load. For the upper port plug, the design-driving load is electromagnetic (EM) forces due to plasma disruptions. In this paper, the dynamic amplification factor (DAF) of the structure is calculated for such EM loads. The bolted joint at the back flange of the plug structure is also considered together with the port extension of the vacuum vessel and its influence on the dynamic behavior is investigated. The analysis results show that the bolted joint reduces the DAF as well as the natural frequency of the structure.

This study was conducted to evaluate the effects of yeast culture (YC) supplementation on the growth performance, apparent nutrient digestibility and caecal microflora of broiler chickens. A total of 360 one-day-old Arbor Acres broiler chickens were randomly assigned to six dietary treatments containing 0.2%, 0.4%, 0.6%, 0.8% and 1% YC. The experiment lasted for 42 days. Diet and faecal samples were collected for analysis of dry matter, crude protein, ether extract, calcium and phosphorus. Caecal microbiota on days 21 and 42 were measured using polymerase chain reaction-denaturing gradient gel electrophoresis (PCR-DGGE) and real-time PCR. Dietary supplementation with YC did not affect feed intake. On day 42, the 0.8% YC group showed optimal growth and feed efficiency, as well as higher levels of apparent digestibility of ether extract, calcium and phosphorus. On day 21, both 0.8% and 1% YC groups exhibited a significant increase in Ruminococcus , Propionibacterium clostridiales , and Bifidobacterium density. The density of Bacteroides in the YC groups was significantly higher than that of the control group. On day 42, the densities of Bacteroides , Sphingomonas and Bifidobacterium were higher in the 0.8% YC group, whereas a significant decrease was observed in the number of Enterobacteriaceae . These results serve as evidence that dietary supplementation with 0.8% YC not only moderately optimized the feed efficiency and the apparent digestibility of ether extract, calcium and phosphorus, but also positively influenced the caecal bacterial density and diversity in broiler chickens. Keywords: Arbor Acres broiler, caecal microflora, yeast culture supplementation

It is necessary to use the same CAD platform for standardization and efficient design collaboration between project partners. ITER has selected CATIA with ENOVIA as the primary CAD and integration tool. During the preparation of the CAD infrastructure, there were several difficulties with respect to information technology (IT). ITER design is classified as mechanical and plant. The procurement arrangement is divided into three types; functional specification, detailed design, and build to print. Therefore, it is important to prepare the suitable prerequisites according to the design type, and to comply with CAD methodologies to avoid trial and error. This paper presents how to overcome the difficulties and how to perform the CAD activities for ITER Korea procurement packages including important matters on a CAD infrastructure in a big project.

ITER will have a set of 45 diagnostics to ensure controlled operation. Many of them are integrated in the ITER ports. This paper addresses the integration process of the diagnostic systems and the approach taken to enable coordinated progress. An overview of the Port Integration hardware introduces the various structures needed for hosting tenant systems inside ITER diagnostics ports. The responsibilities of the different parties involved (ITER Organization and the Domestic Agencies) are outlined. The main challenges for diagnostic port integration engineering are summarized. The plan for a common approach to design and manufacture of the supporting structures, in particular the Port Plug is detailed. A coordinated design including common components and a common approach for neutronic analyses is proposed. One particular port, the equatorial port 11, is used to illustrate the approach.

In this study, we assessed the temporal response of growth hormone (GH)/ghrelin to the intravenous administration of GH releasing hormone (GHRH) in 11- (period 1) and 15-month-old (period 2) Korean native steers, as well as the insulin induction response to glucose administration after completion of the feeding scheme in 11-month-old Korean native steers experiencing stair-step and extended restriction feeding schemes. The experiment was divided into periods 1, 2, 3, and 4 with durations of 3, 2, 4, and 2 months, respectively. The control group (n=9) was fed according to a standard feeding program during all 4 periods. The T1 (n=9; stair-step fed group) was fed a diet with total digestible nutrients (TDN) at concentrations 20% less and more than the TDN concentration fed to the control group in periods 1 and 3 and periods 2 and 4, respectively, whereas the T2 (n=9; extended restricted group) was fed increasing levels of TDN, having concentrations of 30%, 20%, 10% less than and 20% more than the TDN concentration of control group, during periods 1, 2, 3, and 4, respectively. Randomly chosen steers (n=4, total 12 heads) from the C, T1, and T2 groups were used for the experiment of GHRH and glucose administration. Compared to the control group, the T1 showed elevated levels of plasma GH and insulin after GHRH and glucose administration (p

A feeding experiment with 15 lactating goats and 3 dietary treatments was conducted to investigate supplementation of safflower or linseed oil on milk production and the fatty acid (FA) profile of blood plasma and milk, and to measure the mRNA abundance of stearyl CoA desaturase (SCD), lipoprotein lipase (LPL), acetyl-CoA carboxylase (ACC) and fatty acid synthase (FAS) in mammary biopsies. Goats were randomly assigned to one of three treatment groups with five goats per treatment consisting of a basal diet supplemented with chopped alfalfa hay at a level of 299.9 g/kg (dry matter (DM) basis) as the control (CON); CON diet mixed with safflower oil (50 g/kg of TMR DM) as a source of C18:2 (SO) or linseed oil (50 g/kg of TMR DM) as a source of C18:3 (LO). The experiment lasted 8 wks which included a 2 wk adjustment period. Milk fat yield (P

Electromagnetic (EM) loads due to eddy current and halo current during plasma disruptions are evaluated for the ITER diagnostic upper port plug. To reduce strong EM loads acting on the port plug fixed to the vacuum vessel like a cantilever beam, three design options have been considered: removal of the diagnostic first wall, slitting of the diagnostic shield module and recess of the port plug. The main focus of the present study is to examine the efficacy of these options in terms of EM loads on the upper port plug. It is found that making slits is more effective than removing the first wall. It is also shown that the upper port plug needs to be recessed to reduce the EM load induced by halo current.

ITER plasma boundary and first-wall diagnostics are summarized in terms of their physical implementation and physics motivation. The challenge of extracting diagnostic signals while maintaining nuclear shielding is discussed, as well as the problems associated with high levels of erosion and redeposition.

R&D activities currently being undertaken for HCSB TBM include joining technologies of structural material, breeder and reflector pebble material development, the effect of TBM ferritic–martensitic steel on the ripple of toroidal magnetic field, and ceramic coating on graphite pebble. The HIP joining performance of FM steel is evaluated. Lithium ceramic breeder and graphite reflector pebble fabrication methods are under development using special fabrication process, and the initial characteristics of the pebbles are assessed. Silicon carbide coating on graphite pebble is also investigated and its preliminary results are mentioned. Finally, an accurate evaluation of the effect of TBM and ferromagnetic inserts on magnetic field are implemented. The current results of these R&D issues are addressed in this paper.

The diagnostic upper port plug in ITER is fixed to the upper port of the vacuum vessel as a cantilevered beam with bolts and forms a primary vacuum boundary. It needs to be baked out for outgassing before normal operation. This study calculated the required bake-out time and the transient thermal stress during baking for the diagnostic upper port plug. The calculation was done through numerical simulation. The analysis took into consideration the gradual temperature increase of working fluid. In order to look into the effect of radiation heat transfer from the upper port plug to the vacuum vessel port, the upper vacuum vessel port was included in this analysis.

The Republic of Korea is participating in the ITER project as a full member and procuring components for the ITER tokamak and its facility. This paper presents the current stage of preparation of the ITER components to be delivered by Korea including an overview of Korean activities related to the ITER project, as of October 2009.

To assess hydraulic connections between subcomponents of the International Thermonuclear Experimental Reactor (ITER) diagnostic port plug, we investigated the laser welding and ablation cutting process, which can be applied to remote handling maintenance. In this study, laser ablation cutting, which vaporizes a small amount of solid material directly into gas by focusing a laser beam of high-density energy, is adopted in order to overcome the limitation of the normal laser cutting technology that the head should be placed as close to the work piece as possible to blow out melt metal at a distance. Complete cutting of a work piece is obtained by repetitive multi-passes of the laser beam. The welding and cutting process were tested on the sample work pieces and finally on a prototype of a hydraulic connection module for remote handling. The results showed that this process can be a promising candidate for hydraulic connections by remote handling. Furthermore the design of the hydraulic connection module has been updated to resolve some technical difficulties that were found during the test.

At the International Thermonuclear Experimental Reactor (ITER), a neutron activation system is foreseen to measure neutron fluence on the first wall and to evaluate total fusion power from ITER plasma. This system utilizes the method of counting gamma radiation from the metal sample irradiated by the neutron flux at the irradiation end located near the plasma. Evaluation of the operational radioactivity of the sample, which has been induced during ITER operation, is necessary in order to determine sample material, mass, and the appropriate irradiation time. Neutronic calculations are performed to evaluate operational activity of the sample. Activation of the sample is calculated according to the irradiation time for various sample materials such as Si, Al, Ti, Fe, Nb, and Cu and by assuming that the samples are irradiated at the midplane inboard region where the neutron flux is one of the strongest.

A feeding trial was conducted to examine the effect of high-temperature-micro-time (HTMT) processing of diets containing extruded soybean (ESB) in high quantity on milk fat production, metabolic responses, and the formation of conjugated linoleic acid (CLA) and trans-vaccenic acid (TVA). Twenty-one multiparous Holstein cows in mid-lactation were blocked according to milk yield in the previous lactation. Cows within each block were randomly assigned to either normal concentrate or HTMT treated diets containing ESB (7.5% HTMT-ESB and 15% HTMT-ESB). It was hypothesized that the HTMT-ESB would affect the undegradable fatty acids in the rumen and, thus, would modify the fatty acid profile of milk fat. Both 7.5% and 15% HTMT-ESB did not affect milk yield, fat, protein, lactose and solid-not-fat (SNF), but the proportion of cis-9, trans-11 CLA in milk fat was significantly increased by these treatments. Content of TVA in milk fat was not affected by HTMT-ESB. The HTMT-ESB influenced the fatty acid profile in milk fat, but there was little difference between 7.5% and 15% of supplementation. HTMT-ESB feeding significantly decreased the concentration of plasma insulin and glucose, while plasma growth hormone (GH), triglyceride (TG), non-esterified fatty acid (NEFA) and HDL-cholesterol were increased by 7.5% and 15% ESB-HTMT supplementation in comparison to the control group (p 0.05). The present results showed that cis-9, trans-11 CLA production was increased by HTMT treatment of dietary ESB without reduction of milk fat, and the unchanged milk fat and yield was assumed to be associated with the constant level of thyroid hormones, leptin, and IGF-1.

A metabolic study was conducted with four ruminally-cannulated lactating goats (Saanen, 29 weeks lactation, 65± 5 kg) in a 4x4 Latin square design with 4 dietary treatments. The goats were fed a basal mixed diet consisting of 80% concentrate and 20% chopped rye grass hay (DM basis, CON). The goats were also fed the CON diet supplemented with soybean oil at a 5% level of the concentrate (SO), the SO diet supplemented with 0.5% of sodium bicarbonate (SO-B) or the SO-B diet supplemented with 30 ppm monensin (SO-BM). The goats were housed in individual pen and the study was conducted for 8 weeks. An increased molar proportion of propionate (C 3 ) was observed at 1 h (p

A preliminary thermo-hydraulic analysis was performed on the ITER diagnostic upper port plug. Relevant thermal and hydraulic parameters, such as coolant pressure drop, maximum structure temperature and bake-out time, were calculated for normal operation and baking. The upper port plug considered is based on the preliminary generic structure design of Princeton Plasma Physics Laboratory and the Blanket Shield Module (BSM developed in Europe. The diagnostic shield modules are modeled so that the Korean diagnostic procurement package, which includes Vacuum UltraViolet (VUV) spectrometer and neutron activation system, can be integrated The analysis provides design inputs to optimize flow in the cooling channels of the plug. The conjugated heat transfer analysis for the port plug confirms that it is important to secure accurate nuclear heat and accurate electro-magnetic (EM) force for the design of the joining flange between the BSM and the main body. Thermal analysis shows that it will take ten hours for the port plug to reach the bake-out temperature (240 0 C), if the window plate is heated additionally from the rear side.

A 2.56-gigasample-per-second (GSPS) fixed-point fixed-precision dynamic kernel function fast Fourier transform (FFT) with a variable truncation scheme (VTS) is designed for real-time wideband signal detection. Using an Atmel 10-bit analog-to-digital converter (ADC), the two-tone real-time signal detection is verified for a bandwidth of 1.14 GHz with 20-MHz channelization and output throughput rates of 50 ns. The proposed design has an averaged single-signal spurious-free dynamic range (SFDR) of 27.7 dB and the ability to detect a weak input signal at -45 dBm. The overall dynamic range (DR) of the system is 40.6 dB. This is possible for a fixed-precision FFT design due to the embedded VTS to extend the total DR while preserving the instantaneous DR (IDR) relationship. In addition, with an ideal 8-bit ADC, the averaged single-signal SFDR of 32.60 dB and the two-tone signal IDR of 22 dB are achieved. The overall DR is 48.3 dB. The dynamic kernel FFT uses about 57% of the slices available on a Xilinx XC4VSX55 Virtex 4 field-programmable gate array (FPGA). In comparison with alternative implementations based on Xilinx LogicCORE 256-point IP FFT for 8-bit data, the processing time and the overall DR are considerably superior. Additional case studies that applying the windowing function and the Taylor-series-based square root approximation show favorable results utilizing the VTS for real-time data acquisition and signal-enhancement algorithms for computing high-bit-width data while minimizing the hardware.

The thermal shield system of ITER plays the role of reducing heat loads transferred by thermal radiation and conduction from warm components to the components and structures that operate at 4.5 K. In the design of thermal shields, it is of importance to ensure that they maintain thermal loads within the specified design criteria. In the present work, a study is conducted on thermal analyses in order to confirm that the thermal shield design can accommodate the thermal loads during the plasma operation state and the baking state of the ITER vacuum vessel. Design of the cooling tube layout of a vacuum vessel thermal shield is followed based on the results of thermal analyses. It is demonstrated that the present results can be applied to the detailed design of the ITER thermal shield system.

Based on the design done by the ITER international organization (ITER-O) and other participant teams, the more detail engineering design of the ITER vacuum vessel port and support is progressed by the Korea ITER project team. In this work, the recent design elaboration and manufacturing feasibility study from 2006 mainly focused on the equatorial and lower port are reported. The fabrication status and test plan of vacuum vessel support mock-up are also introduced.

A study is conducted on the conceptual design of the structure and cooling channels of the upper port plug of International Thermonuclear Experimental Reactor (ITER). Modification of the earlier port plug design is made and a simple fabrication method is proposed. It is shown that the newly designed port plug can accommodate the installation of both diagnostic and electron cyclotron heating (ECH) devices. Design assessment is carried out through structural and thermo-hydraulic analyses. Results of the analyses show that the port plug structure is stable against one of the most severe plasma events and the total pressure drop of the coolant is within the allowable level.

The present study was conducted with four ruminally canulated Holstein cows to observe the effects of monensin or fish oil on diet fermentation and production of conjugated linoleic acids (CLAs) in the rumen when fed diets supplemented with soybean oil and sodium bicarbonate. Cows of the control treatment were fed a basal diet (CON) consisting of 60% commercial concentrate and 40% chopped rye grass hay. Cows of other treatments were fed the same diet as CON, but the concentrate was supplemented with 7% of soybean oil and 0.5% of sodium bicarbonate (SO-B), SO-B supplemented with monensin (30 ppm, SO-BM) or concentrate supplemented with 6.3% of soybean oil, 0.5% of sodium-bicarbonate, 30 ppm of monensin and 0.7% of fish oil (SO-BMF). Dry matter (DM) intake of the cows was significantly (p

The numerical solution is obtained for unsteady two-dimensional fluid flow and heat transfer in a confined impinging slot jet using the finite volume method. In order to consider the effect of Reynolds number and height ratio on the flow and temperature fields in the channel, the numerical simulations were performed for different Reynolds numbers of 50–500 and different height ratios of 2–5. The critical Reynolds number, beyond which the flow and thermal fields change their state from steady to unsteady, depends on the Reynolds number and height ratio. The unsteadiness gives a big impact on the flow and temperature fields and as a result the pressure coefficient, skin friction coefficient and Nusselt number in the unsteady region show different characteristics from those in the steady region.

The upper port #18 (UP18) in ITER hosts three diagnostic systems: the neutron activation system, the Vacuum Ultra-Violet spectrometer system, and the vertical neutron camera. These diagnostics are integrated into three infrastructures in the port: the upper port plug, interspace support structure and port cell support structure. The port integration in UP18 is at the preliminary design stage and the current design of the infrastructure as well as the diagnostic integration is described here. The engineering issues related to neutron shielding and maintenance are addressed and the design approach is suggested.

The present study was conducted to investigate the supplementation effects of C 18.2 rich-soybean oil or C 18.3 rich-perilla oil (7% of total diet, DM basis) for 12 weeks on plasma metabolites, fatty acid profile, in vitro lipogenesis, and activities of LPL and FAS in adipose tissue of sheep. The treatments were basal diet (Control), C 18:2 rich-soybean oil supplemented diet (SO-D) and C 18:3 rich-perilla oil supplemented diet (PO-D). All the sheep were fed the diets consisting of roughage to concentrate in the ratio of 40:60 (DM basis). Oil supplemented diets (SO-D and PO-D) slightly increased contents of triglyceride (TG) and total cholesterol (TC), proportions of both cis-9 trans-11 and trans-10 cis-12 CLA and TVA, but lowered (p

In this review article, we are going to explain the recent development of lithium secondary batteries for a cellular phone. There are three kinds of rechargeable batteries for cellular phones such as nickel-cadmium, nickel-metal hydride, and lithium ion or lithium ion polymer. The lithium secondary battery is one of the most excellent battery in the point of view of energy density. It means very small and light one among same capacity batteries is the lithium secondary battery. The market volume of lithium secondary batteries increases steeply about 15% annually. The trend of R&D is focused on novel cathode materials including , novel anode materials such as lithium titanate, silicon, and tin, elecrolytes, and safety insurance.

Milk consumption, dry feed intake, body weight (BW) gain, occurrence of diarrhea, and selected blood metabolites were studied in female Holstein calves fed milk either through conventional or step-down (STEP) methods. In conventional method, the calves (n = 20) were fed colostrum and then milk at the rate of 10% of BW for the entire period of 45 d. In STEP method, the calves (n = 20) were given colostrum and then milk for 25 d at the rate of 20% of BW, which was reduced (between d 26 to 30) to 10% of BW for the remaining 15 d. The calves fed through conventional and STEP methods were weaned gradually by diluting milk with water between d 46 and 50. Feed intake and BW of the calves were monitored until 90 d of age. The STEP calves consumed 92.3, 19.4, and 62.4% more milk than conventionally fed calves during pre-STEP (d 1 to 30), post-STEP (d 31 to 50), and preweaning (d 1 to 50) periods, respectively. Consumption of starter and hay were greater during the pre-STEP period and lesser during the post-STEP and postweaning (d 51 to 90) periods in calves provided milk using conventional method compared with STEP-fed calves. Body weight gain, dry matter intake, and feed efficiency of calves were greater in those on the STEP method than on the conventional method. Lesser blood glucose and greater blood urea nitrogen at weaning (d 50) and postweaning (d 60) possibly indicated a better functioning rumen in calves fed milk through The STEP method than those fed conventionally. Occurrence of diarrhea was higher during wk 3 and 4 of age in calves fed milk through conventional method compared with STEP-fed calves. In conclusion, STEP milk feeding may prevent the problems of depressed solid feed intake associated with ad libitum milk feeding and of poor BW gain with conventional milk feeding in dairy calves.

Diagnostics play a very important role in the modern Tokamak where optimum performance is essential. To achieve this, the device must be equipped with reliable and robust sensors and instrumentation that allow the operation envelope to be fully explored. Development of these diagnostics to maintain this reliability is necessary. Further to the development, the systems must be integrated in a way that maintains their performance while simultaneously satisfying the key requirements needed for safety and tokamak operation. ITER will have 50 diagnostics; almost all of which are utilized primarily for the real-time operation of the tokamak. While there is still much work to do, to date, significant progress has been made in the development of these systems. The work load for the developments is shared across all the ITER partners. This paper focuses on the challenges for the integration of the systems.