• Title/Summary/Keyword: Co-exposure

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Adsorption properties of MgO protective layer in AC PDP

  • Manakhov, Anton;Nikishin, Nikolay;Hur, Min;Heo, Eun--Gi
    • 한국정보디스플레이학회:학술대회논문집
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    • 2008.10a
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    • pp.384-387
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    • 2008
  • We have studied the adsorption of contaminations on the MgO protective layer by Thermal Desorption Spectrometry (TDS). The result shows that the increase in exposure time, MgO thickness and humidity multiply the quantity of adsorbed contaminations. It is also found that the desorption activation energy and contamination quantity is decreased by the additional firing process of MgO layer under oxygen environment.

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Exposure to Ozone and TVOCs during Shipyard Welding and the Adequacy of RPE (조선소 용접작업 중 오존 및 TVOCs의 노출평가와 사용 호흡보호구의 적합성)

  • Han, Don-Hee;Kim, Dong Hwan
    • Journal of Korean Society of Occupational and Environmental Hygiene
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    • v.28 no.2
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    • pp.200-210
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    • 2018
  • Objectives: The purpose of this study is to assess the exposure to ozone and total volatile organic compounds(TVOCs) generated during welding work at a shipyard and recommend respiratory protective equipment(RPE) adequate against these hazards. Method: Ozone was collected for about 30 minutes at two-minutes intervals using a direct reading instrument, specifically an ozone analyzer(Serinus 10, Ecotech, Australia). TVOCs were collected for about 30 minutes at three-minute intervals using a portable GC (Alpha 115, Synspec BV, the Netherlands), and were determined simultaneously by area sampling at the welding plume closest to the welder's breathing zone. The total measurements were 162 for ozone($CO_2$ welding 47, TIG 60, stick 55), and 136 for TVOCs($CO_2$ 65, TIG 50, stick 21). Based on these measurements, a literature survey was conducted to assess the adequacy of RPE. Results: Relative to Korean OEL, measurements above STEL 0.2 ppm were 23.4% for $CO_2$, 63.3% for TIG and 14.5% for stick welding. There were significant differences(p=<0.0001) among welding types. Compared with ACGIH peak exposure of 0.4 ppm for ozone, which is not applied in Korea, $CO_2$ welding exceeded it by 10.6%, TIG by 40.0% and stick by 7.3%. Although it was not feasible to compare them directly since there are no Korean OEL, TVOCs had very high levels similar to the concentrations before moving into a new apartment and about 10-20 times the indoor air quality recommendations for some individual measurements. Conclusions: As ozone removal RPE has been recommended in welding environments for a long time(Lunau, 1967), this fact was demonstrated based on the results of the on-site work environment measurements(ozone and TVOCs). In conclusion, for all welding at a shipyard, gas/vapor and particulate combination RPE are recommended. If this is not possible, it should at least be present for TIG welding.

An Effects of Radiation Dose Assessment for Radiation Workers and the Member of Public from Main Radionuclides at Nuclear Power Plants (원전에서 발생하는 주요 방사성핵종들이 방사선작업종사자와 원전 주변주민의 피폭방사선량 평가에 미치는 영향)

  • Kim, Hee-Geun;Kong, Tae-Young;Jeong, Woo-Tae;Kim, Seok-Tae
    • Journal of Radiation Protection and Research
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    • v.35 no.1
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    • pp.12-20
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    • 2010
  • In a primary system at nuclear power plants (NPPs), various radionuclides including fission products and corrosion products are generated due to the complex water conditions. Particularly, $^3H,\;^{14}C,\;^{58}Co,\;^{60}Co,\;^{137}Cs,\;and^{131}I$ are important radionuclides in respect of dose assessment for radiation workers and management of radioactive effluents. In this paper, the dominant contributors of radiation exposure for radiation workers and the member of public adjacent to NPPs were reviewed and the process of dose assessment attributable to those contributors were introduced. Furthermore, the analysis for some examples of radiation exposure to radiation workers and the public during the NPP operation was carried out. This analysis included the notable precedents of internal radiation exposure and contamination of demineralized water occurred in Korean NPPs. Particularly, the potential issue about the dose assessment of tritium and carbon-14 was also reviewed in this paper.

Changes in Firmness of Apples during Exposure to Room Temperature after CA storage (CA 저장한 사과의 상온방치시 경도변화)

  • Kim, Dong-Man;Shin, Hyun-Kyung
    • Journal of the Korean Society of Food Science and Nutrition
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    • v.15 no.1
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    • pp.9-14
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    • 1986
  • Fuji and Jonathan apples were stored at cold room and at CA storage conditions of $3%O_2-2%CO_2$ for Jonathan and $4%O_2-3%CO_2$ for Fuji for 8 months, and then tranferred to air at $20^{\circ}C$, 70%RH to compare the some factors related to texture of the apples stored at different storage conditions during exposure at $20^{\circ}C$. Total pectin content and firmness of the apples reduced, considerably with concomitant increases of water-soluble pectin content and polygalacturonase activity during exposure at $20^{\circ}C$ after storage. And the changes were much more serious in the first 5 days than any other period and in the apples stored at cold room, especially in Jonathan than the apples stored at CA storage conditions. From the sensory test the apples stored at cold room maintained acceptable quality for 5days after removal from storage condition. The acceptability from the test was lenghtened for more than 5 days in Jonathan and more than 10 days for Fuji stored at CA storage conditions. when compared with those of the apples stored at cold room.

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The Study on the Image Quality and Patient Exposure Dose of Chest Radiography in Korea (흉부촬영시 피폭선량과 화질에 관한 조사연구)

  • Lee, Sun-Sook;Huh, Joon
    • Journal of radiological science and technology
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    • v.18 no.2
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    • pp.49-59
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    • 1995
  • Recently, general radiography became to variety because of the continuous development of Inverter type generator and ortho chromatic system. Therefore, we must re-evaluate about patient exposure dose and image quality. I studied about chest radiography which has frequency among general radiography being used during FEB. to AUG., 1994 over 151 medical facilities from medical facilities that are located in Seoul area. The result obtained were as follows ; 1) The rectification method of the generator were employing mainly single phase full wave in 82.8 %, three phase full wave in 11.26 % and Inverter type in 4.64 % and condenser type is 1.32 %. 2) Exposure kV was used below 80 kV in most medical facilities and 21.8 % of the medical facilities was using high tube voltage higher than 120 kV. 3) The exposure time was used below the 0.05 sec in 28.4 %, in 29.8 % of the medical facilities used above 0.1 sec. 4) The usage frequency of the added filter is 15.3 %, and among them compound filter was used only 4 %. 5) Rare earth screen was used in 37.7 %. 6) The average skin entrance dose was 0.25 mSv, the range of dose is $0.05{\sim}0.79\;mSv$ in each medical facilities. 7) The average density of the lung field is 1.76, 0.49 in lung side, 0.30 in mediastinum and 0.37 in heart shadow. Therefore it is required to improve all of these for increasing image quality and reducing patient exposure dose as soon as possible.

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Radiological Safety Assessment for a Near-Surface Disposal Facility Using RESRAD-ONSITE Code

  • Jang, Jiseon;Kim, Tae-Man;Cho, Chun-Hyung;Lee, Dae Sung
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.19 no.1
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    • pp.123-132
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    • 2021
  • Radiological impact analyses were carried out for a near-surface radioactive waste repository at Gyeongju in South Korea. The RESRAD-ONSITE code was applied for the estimation of maximum exposure doses by considering various exposure pathways based on a land area of 2,500 ㎡ with a 0.15 m thick contamination zone. Typical influencing input parameters such as shield depth, shield materials' density, and shield erosion rate were examined for a sensitivity analysis. Then both residential farmer and industrial worker scenarios were used for the estimation of maximum exposure doses depending on exposure duration. The radiation dose evaluation results showed that 60Co, 137Cs, and 63Ni were major contributors to the total exposure dose compared with other radionuclides. Furthermore, the total exposure dose from ingestion (plant, meat, and milk) of the contaminated plants was more significant than those assessed for inhalation, with maximum values of 5.5×10-4 mSv·yr-1 for the plant ingestion. Thus the results of this study can be applied for determining near-surface radioactive waste repository conditions and providing quantitative analysis methods using RESRAD-ONSITE code for the safety assessment of disposing radioactive materials including decommissioning wastes to protect human health and the environment.

Comparison of Skin Injury Induced by β- and γ-irradiation in the Minipig Model

  • Kim, Joong-Sun;Jang, Hyosun;Bae, Min-Ji;Shim, Sehwan;Jang, Won-Seok;Lee, Sun-Joo;Park, Sunhoo;Lee, Seung-Sook
    • Journal of Radiation Protection and Research
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    • v.42 no.4
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    • pp.189-196
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    • 2017
  • Background: The effects of radiation on tissues vary depending on the radiation type. In this study, a minipig model was used to compare the effects of ${\beta}$-rays from $^{166}Ho$ and ${\gamma}$-rays from $^{60}Co$ on the skin. Materials and Methods: In this study, the detrimental effects of ${\beta}$- and ${\gamma}$-irradiation on the skin were assessed in minipigs. The histopathological changes in the skin from 1 to 12 weeks after exposure to 50 Gy of either ${\beta}$- (using $^{166}Ho$ patches) or ${\gamma}$- (using $^{60}Co$) irradiation were assessed. Results and Discussion: The skin irradiated by ${\beta}$-rays was shown to exhibit more severe skin injury than that irradiated by ${\gamma}$-rays at 1-3 weeks post-exposure; however, while the skin lesions caused by ${\beta}$-rays recovered after 8 weeks, the ${\gamma}$-irradiated skin lesions were not repaired after this time. The observed histopathological changes corresponded with gross appearance scores. Seven days post-irradiation, apoptotic cells in the basal layer were detected more frequently in ${\beta}$-irradiated skin than in ${\gamma}$-irradiated skin. The basal cell density and skin thickness gradually decreased until 4 weeks after ${\gamma}$- and ${\beta}$- irradiation. In ${\beta}$-irradiated skin lesions, and the density and thickness increased sharply back to control levels by 6-9 weeks. However, this was not the case in ${\gamma}$-irradiated skin lesions. In ${\gamma}$-irradiated skin, cyclooxygenase-2 (COX-2) was shown to be expressed in the epidermis, endothelial cells of vessels, and fibroblasts, while ${\beta}$-irradiated lesions exhibited COX-2 expression that was mostly limited to the epidermis. Conclusion: In this study, ${\beta}$-rays were shown to induce more severe skin injury than ${\gamma}$-rays; however, the ${\beta}$-rays-induced injury was largely repaired over time, while the ${\gamma}$-rays-induced injury was not repaired and instead progressed to necrosis. These findings reveal the differential effects of ${\gamma}$- and ${\beta}$-irradiation on skin and demonstrate the use of minipigs as a beneficial experimental model for studying irradiation-induced skin damage.

Effect of Ginseng Saponins on Neurotransmitter System Damage in Carbon Monoxide and Aging Rats -Effect on the Memory Impairment- (인삼 사포닌이 일산화탄소와 노화에 의한 신경전달계 변화에 미치는 영향 -기억력 장해에 미치는 영향-)

  • Yun, Hae-Chung;Shin, Jeung-Hee;Choi, Hyun-Jin;Yun, Jae-Soon
    • YAKHAK HOEJI
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    • v.36 no.1
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    • pp.56-65
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    • 1992
  • The present study examined the effects of carbon monoxide (CO) intoxication and aging on learning and memory deficit in young($5{\sim}8$ weeks) and aged($52{\sim}66$ weeks) mice, using the step down and step through passive avoidance failure techniques. We also investigated the effects of ginseng saponins on memory deficit. Significant decrease in memory registration, retention and retrieval function in young mice and decrease in memory registration and retention function in aged mice were observed. Normal young mice were apt to perform to a great degree of passive avoidance response than normal aged mice, but there was no difference between both groups by CO exposure. Administration of ginseng saponins showed an improvement on passive avoidance failure induced by CO exposure.

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Flow Characteristics Analysis for the Chemical Decontamination of the Kori-1 Nuclear Power Plant

  • Cho, Seo-Yeon;Kim, ByongSup;Bang, Youngsuk;Kim, KeonYeop
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.19 no.1
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    • pp.51-58
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    • 2021
  • Chemical decontamination of primary systems in a nuclear power plant (NPP) prior to commencing the main decommissioning activities is required to reduce radiation exposure during its process. The entire process is repeated until the desired decontamination factor is obtained. To achieve improved decontamination factors over a shorter time with fewer cycles, the appropriate flow characteristics are required. In addition, to prepare an operating procedure that is adaptable to various conditions and situations, the transient analysis results would be required for operator action and system impact assessment. In this study, the flow characteristics in the steady-state and transient conditions for the chemical decontamination operations of the Kori-1 NPP were analyzed and compared via the MARS-KS code simulation. Loss of residual heat removal (RHR) and steam generator tube rupture (SGTR) simulations were conducted for the postulated abnormal events. Loss of RHR results showed the reactor coolant system (RCS) temperature increase, which can damage the reactor coolant pump (RCP)s by its cavitation. The SGTR results indicated a void formation in the RCS interior by the decrease in pressurizer (PZR) pressure, which can cause surface exposure and tripping of the RCPs unless proper actions are taken before the required pressure limit is achieved.