• Current Photovoltaic Research
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• v.6 no.3
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• pp.69-73
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• 2018

PV system is consisted with PV module, inverter and BOS(balance of system). To have robustic operation more than 20 years, the expected and guaranteed durability and reliability of products should be met. Almost components of PV system are qualified through IEC standards at test laboratory. But the qualification certificate of product does not ensure long-term nondefective operation. PV module's expected life time is nowadays more than 20 years and annual maximum power degradation ratio would be less than -1%. But the power degradation ratio is basically based on real data more than several years' record. Developing test method for ensuring annual maximum power degradation ratio is very need because there are many new products every month with new materials. In this paper, we have suggested new test method under continuous artificial light irradiation test condition for analyze expected maximum power drop ratio.

• Journal of Welding and Joining
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• v.23 no.6
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• pp.43-48
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• 2005

This work was carried out to obtain sound welds and to select a most suitable binary metal joint among three different dissimilar binary metal combinations such as Zr-4/Ta, Mo/Ta and Ti/Ta(seal tube/sensor sheath) joints fur the instrumented nuclear fuel irradiation test. To do this, Taguchi experimental method was employed to optimize the experimental data. In addition, metallography, micro-focus x-ray radiography and hardness test were conducted to examine the welds. From the weld bead appearance, penetration depth and bead width as well as weld defects standpoint, Zr-4/Ta joint is suggested for the circumferential joining between a seal tube and a sensor sheath. The optimized welding parameters based on Zr-4/Ta joint are suggested as well.

• Journal of Digital Convergence
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• v.12 no.6
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• pp.433-438
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• 2014

This study aims to get more accurate and objective result by quantifying the result for the sperm changes through the quantitative analysis by the image processing based on the image obtained microscopically for the testicle cell and sperm change appeared with the passage of time when the radiation is irradiated to the white rat testicle. This study has targeted the white rat of 8 weeks lifespan, the X-ray of 6 MV with 1 time of 2 Gy has been irradiated to the whole body. The testicles of 5 rats at each test group immediately after irradiation, after 2 hours of irradiation, 4 hours, 8 hours and 24 hours has been respectively extracted targeting all 30 white rats of normal control group not irradiated by the radiation and the test group. The state of testicle cell and sperm has been observed in the normal control group and the test group by implementing Periodic acid Schiff dyeing after extraction. 24 hours after irradiation, a gradual decrease in sperm count and testicular cells qualitatively and quantitatively that were identified as significant.

• The Journal of Korean Society for Radiation Therapy
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• v.13 no.1
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• pp.91-103
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• 2001

In those patients who underwent radiation therapy with 10 MV X-ray for bone marrow transfer, compared the effect of high dose irradiation on peripheral blood were investigated in randomly selecting 18 patients. thus, changes in the levels of peripheral blood (WBC, Seg. neutrophil, Lymphocyte, RBC, Hemoglobin, Hematocrit ratio, GOT, GPT) were observed for 25 days after irradiation with the peripheral blood levels before irradiation in these patients and in 32 controls. Among changes in peripheral blood, the level of WBC was $8.63\%$ after radiation therapy with as much decrease as $0.22{\times}103{\pm}0.19{\times}103/mm^3$ compared with $2.51{\times}103{\pm}1.29{\times}103/mm^3$ before radiation therapy, and was only $6.35\%$ of $7.17{\times}103/mm^3{\pm}1.46{\times}103/mm^3$ in the controls, showing statistical significance (P<0.01, r2=0.9151). In the morphologic test of WBC, the level of Seg. neutrophil was decreased as much as to $20.53\%$ with $14.17{\pm}21.60\%$ compared with $69.00{\pm}25.60\%$ before irradiation, and decreased down to $24.39\%$ compared with $58.09{\pm}7.62\%$ in the controls (P<0.05, r2=0.6316). The number of lymphocyte increased as much as 3.94 folds at $79.91{\pm}27.30\%$ compared with $20.29{\pm}21.15\%$ before irradiation and was 2.39 times higher than $33.46{\pm}6.79\%$ in the controls (P<0.05, r2=0.7337). Although the change in the number of RBC was little with $3.18{\times}106{\pm}0.41{\times}106/mm^3$ before irradiation and $4.66{\times}106{\pm}0.43{\times}106/mm^3$ in the controls, no statistical significance was present (P>0.05). In addition, The number of hemoglobin was low compared with before irradiation and with the controls, but none showed statistical significance (P>0.05). Similarly, although the hematocrit ratio was low compared with before irradiation and with the controls, no statistical significance was present (P>0.05). In the values of the histologic examinations GOT and GPT, there is statistical significance between those from with before irradiation and with the controls (P<0.05). Thus, among peripheral blood, the number of WBC decreased drastically for a certain period after total body irradiation with high dose radiation, and the levels of Seg. neutriphil and lymphocyte decreased significantly after irradiation in the lymphocyte morphologic test. The results of the present study suggest that the possibility of developing the first to determine initially those patients who might develop radiation acute impairment using the usual peripheral blood test of patients to be exposed to high dose irradiation.

• Proceedings of the Korean Society of Precision Engineering Conference
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• 2007.06a
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• pp.353-354
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• 2007

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.5 no.4
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• pp.309-322
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• 2007

This study deals with the irradiation effects on some selected components which are being used in an Advanced Spent Fuel Conditioning Process (ACP). Irradiation test components have a higher priority from the aspect of their reliability because their degradation or failure is able to critically affect the performance of an ACP equipment. Components that we chose for the irradiation tests were the AC servo motor, potentiometer, thermocouples, accelerometer and CCD camera. ACP facility has a number of AC servo motors to move the joints of a manipulator and to operate process equipment. Potentiometers are used for a measurement of several joint angles in a manipulator. Thermocouples are used for a temperature measurement in an electrolytic reduction reactor, a vol-oxidation reactor and a molten salt transfer line. An accelerometer is installed in a slitting machine to forecast an incipient failure during a slitting process. A small CCD camera is used for an in-situ vision monitoring between ACP campaigns. We made use of a gamma-irradiation facility with cobalt-60 source for an irradiation test on the above components because gamma rays from among various radioactive rays are the most significant for electric, electronic and robotic components. Irradiation tests were carried out for enough long time for total doses to be over expected threshold values. Other components except the CCD camera showed a very high radiation hardening characteristic. Characteristic changes at different total doses were investigated and threshold values to warrant at least their performance without a deterioration were evaluated as a result of the irradiation tests.

• Nuclear Engineering and Technology
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• v.43 no.1
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• pp.19-24
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• 2011

These experimental studies are carried out to build a database for analyzing fuel performance in nuclear power plants. In particular, this study focuses on the mechanical and irradiation properties of three kinds of zirconium alloy (Alloy A, Alloy B and Alloy C) irradiated in the HANARO (High-flux Advanced Neutron Application Reactor), one of the leading multipurpose research reactors in the world. Yield strength and ultimate tensile strength were measured to determine the mechanical properties before and after irradiation, while irradiation growth was measured for the irradiation properties. The samples for irradiation testing are classified by texture. For the irradiation condition, all samples were wrapped into the capsule (07M-13N) and irradiated in the HANARO for about 100 days (E > 1.0 MeV, $1.1{\times}10^{21}\;n/cm^2$). These tests and results indicate that the mechanical properties of zirconium alloys are similar whether unirradiated or irradiated. Alloy B has shown the highest yield strength and tensile strength properties compared to other alloys in irradiated condition. Even though each of the zirconium alloys has a different alloying content, this content does not seem to affect the mechanical properties under an unirradiated condition and low fluence. And all the alloys have shown the tendency to increase in yield strength and ultimate tensile strength. Transverse specimens of each of the zirconium alloys have a slightly lower irradiation growth tendency than longitudinal specimens. However, for clear analysis of texture effects, further testing under higher irradiation conditions is needed.

• Journal of Ceramic Processing Research
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• v.20 no.4
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• pp.363-371
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• 2019

In this study, physical properties of normal concrete, magnetite concrete, EAF concrete, and EAF concrete with added iron powder were evaluated and a feasibility of radiation shielding is also evaluated through irradiation tests against X-rays and gamma-rays. While the unit weight of EAF concrete (3.21 t/㎥) appeared lower than that of magnetite concrete (3.50 t/㎥), the results in compressive strength of EAF concrete were greater than those in magnetite and normal concrete. While the radiation transmission rate of normal concrete reaches 26.0% in the X-ray irradiation test, only 6.0% and 9.0% of transmission rate were observed in magnetite concrete and linear relationship with unit volume weight and radiation shielding. In the gamma-ray irradiation test, the performance of EAF and magnetite concretes appeared to be similar. Through the results on the excellent physical properties and radiation shielding performance a potential applicability of EAF concrete to radiation shielding was verified.

• The Journal of Korean Academy of Prosthodontics
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• v.38 no.3
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• pp.291-309
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• 2000

Statement of problem. There were several studies on the effects of irradiation to peri-implant bone tissue. However, no clear biological effect of irradiation on peri-implant bone tissue was reported yet. Purpose. This study compared the effect of irradiation on the surrounding tissue of a HA-coated implant fixture with controls. Material and methods. 6 Steri-Oss implants were implanted into the femur of 6 mongrels. The implanted dogs were divided into three groups and received irradiation. After 1 month, 2months and 4 months healing period, the histologic examination and mobility test and digital radiographic imaging analyses were performed to compare the control and experimental group respectively. Results. The irradiated group showed slower healing than control group in light microscopic observations. The mobility test demonstrated significant less number (Periotest) in control group than that of irradiated groups. The digital radiographic imaging analysis showed that the bone density of irradiated group was higher than control group. Conclusion. Generally, control group showed favorable biological response and less mobility than irradiated group. The conflict result of bone density value were measured by the digital radiographic imaging analysis. The digital radiographic imaging analysis needs more research in future.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.544-548
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• 2003

The Irradiation test of bar code label tagged on radioactive waste container was done to determine the effect of radiation. Low and medium radioactive waste is that below total activity of 4,000 Bq/g according to the Korean nuclear law. The irradiation amount to radiate bar code label tagged on radioactive waste container was calculated by MCNP-4b computer code. The nuclide such as Co-60 and Cs-137 was assumed to contribute 50% of total activity. Real irradiation amount for bar code label was finally calculated by the dimensions of the container and the bar code label. The Identification of post and the physical deflection of irradiated bar code label was tested by the bar code reader. The coated bar code label was suitable to use on low and medium radioactive waste container.