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      • 국내 원자력발전소의 사용후핵연료 선원항 평가에 관한 연구

        윤인식,정운관,김성영,염유선,심재학 조선대학교 에너지.자원신기술연구소 2003 에너지·자원신기술연구소 논문지 Vol.25 No.2

        우리나라에서도 원자력발전이 상용화된지 이십여년을 넘어서면서 원자력발전을 하고 있는 다른 나라와 마찬가지로 사용후핵연료 관리가 국가적인 문제로 심각히 대두되고 있다. 중간저장 시설은 1997년부터 운영예정이었으나 현재 그의 부지가 아직 확보되지 못한 상태에서 그 운전개시 시점이 불확실하다. 그리고 중간저장 이후의 사용후핵연료 정기관리 전략이 아직 마련되어 있지 못한 실정이다. 그러므로 발전소에서 발생되는 사용후핵연료 양과 그에 따른 선원항 평가는 반드시 선행되어야 할 것이다. 이제 본 연구에서는 국내 사용후핵연료 형태중 17×17에 대해서 농축도와 연소도 그리고 냉각시간별로 선원항 평가를 하였다. 사용후핵연료 선원항 평가를 위해 미국 Nuclear Regulatory Commission(NRC)의 인·허가 코드인 SCALE 코드를 이용하였다. 선원항 평가는 SCALE 코드의 모듈을 이용하였다. 선원항 평가 결과 농축도와 3.5 w/o와 연소도 35 GWD/MTU 일때 Cooling Time 0.3년은 7.5651E+16, 1년 2.8954E+16, 3년 9.8242E+15, 5년 5.4000E+15, 10년 3.0945E+15으로 계산되었으며, Cooling Time이 0.3년일때와 10년일때의 Source Term이 크게 차이가 남을 알 수 있었다. 방사선량율은 10 ㎝부터 500 ㎝ 까지 거리에 따라 선량율에 대하여 10 ㎝ 4.8365E+03(㏉/hr)에서 500 ㎝ 7.8456E+01으로 감소함을 알 수 있었다. 현재 국내 사용후핵연료에 대한 선원항 평가가 이루어지지 않았으며, Data Base 구축이 기초단계 이므로 이러한 기초자료는 추후 저장조가 건설되면 사용후핵연료 안전성과 관련하여 사용할 수 있는 것이고 기초 Data Base구축하는데 이용할 수 있을 것이다 As nuclear power has been used in our country over 20 years, spent fuel management is raised seriously as one of the national`s problems, which lies in similar situation to other countries having nuclear power plants. An interim storage facility has been planned to operate in 1997, it is highly uncertain whether this facility will start to operate by the time because the site has not been decided yet. After the intermediate storage, the spent fuel periodical management strategy has not prepared yet. Therefore it has to be preceded that the spent fuel quantity which is happening at the power station and the following source term. Now the main have evaluated the source term according to enrichment, burn-up, and cooling time for 17×17 of spent fuel form. I used the SCALE code which were certified by Nuclear Regulatory Commission(NRC) for the source term calculations of Spent Fuel. The source term was calculated, which reflected the feature of target nuclear fuel using ORIGEN-S, a module of the SCALE Code, and the exposure dose rates were calculated by using the QADS modules, considering the geometry. When the enrichment in the evaluated result of source term is 3.5 w/o and the burn-up is 35 GWD/MTU, the cooling time 0.3year is 7.561E+16(photon/second), 1year 2.8954E+16, 3year 9.8242E+15, 5year 5.400E+15, 10year 3.0945E+15 and found that the big difference in Photon Spectrum of cooling time 0.3year and 10year. I have found that radiation dose rate is decreased in 10㎝ 4.8365E+03(㏉/hr) into 500 ㎝ 7.8456E+01 for dose rate according to distance from 10 ㎝ to 500 ㎝. It is not made the source term evaluation on the domestic spent fuel, and since the data base construction is basic level, some time later, if the storage place is constructed, in connection with the safety, these basic data can be used and we can construct these basic data base.

      • A COMPARISON AND STUDY FOR THE PROCESSING ABILITY OF LIQUID RADIOACTIVE WASTE USING ION-EXCHANGE DEMINERALIZER AND EVAPORATOR

        Yeom, Yu-Sun,Kim, Soong-Pyung,Yun, In-Sik,Kim, Sung-Young 조선대학교 에너지.자원신기술연구소 2003 에너지·자원신기술연구소 논문지 Vol.25 No.2

        Most of the low-level liquid radioactive wastes generated from PWR plants are classified into high or low total suspended solid(HTDS or LTDS), radio-chemical waste and radioactive laundry waste. Although the evaporation process has a high decontamination ability, it has several problems such as corrosion, foaming, and congestion. A new liquid waste disposal process using the ion-exchange demineralizer(IED) has been introduced intothe Yong-gwang NPP #5 and 6 to complement the current evaporation process. To determine the differences, these two methods have been compared in this study. Those aspects compared here were the released radioactivity volume of the liquid radioactive wastes, The dose of off-site residents, the decontamination factor, and the amount of the solid radioactive wastes. While it was expected that the liquid radioactive waste volume in the evaporating system would be 20 percent higher than in the IED, the actual volume of the liquid radioactive wastes per year in evaporating system was 0.473 mCi, 1.098mCi, approximately 2.32 times lower than that of IED. The dose of off-site residents was 2.97E-06 mSv with the evaporating system, and 6.47E-06mSv with IED. The decontamination factor(DF) of the evaporatoris, in many cases, far lower than the lower limits of detection(LLD) with the Ge-Li detector. Due to the lower level of concentration of the liquid wastes collected from the liquid radwastesystem, the decontamination factor of IEDis very low. Since there is not enough data on the amount of solid radioactive wastes generated by the evaporation processing system, the comparison has been conducted on the basis of the design, and the result was that the evaporating system generated 42% more of wastes than IED.

      • KCI등재

        An Experimental Research on Uniform Corrosion of Inconel 600 and 690 Tubing Material

        Yu-Sun Yeom,Jung Lae Hwang,In-Sub Jun,Soong-Pyung Kim,Jang-Hee Yoon 한국방사성폐기물학회 2006 방사성폐기물학회지 Vol.4 No.2

        본 논문은 국내 PWR 발전소에서 S/G tube 재질로 사용되고 있는 Inconel 600 및 690에 대한 부식 실험을 수행함으로써 작업자들의 주요 피폭원인 의 생성량을 예측하고자 하였다. 이를 위해 Inconel 600 및 690 재질로 총 12개의 시편을 제작하여 실제 발전소의 운전조건과 유사하거나 가혹한 조건에서 전면 부식실험을 pH별로 20일씩 총 60일간 수행하였고, 실험 결과를 정량적으로 분석하기 위해 GDS(Glow Discharge Spectrometer) 장비를 사용하였다. GDS 장비를 이용하여 정량적으로 분석한 결과 pH 7 및 9에서는 Inconel 600이 Inconel 690에 비해 부식이 잘 되는 것으로 나타난 반면, pH 4에서는 Inconel 690이 부식이 더 잘 되는 것으로 평가되었다. 이러한 경향을 보이는 것은 과도상태의 영향이 과도하게 반영된 것에 기인한 것으로 비교적 정확한 결론을 도출하기 위해서는 장시간의 부식 실험을 수행함으로써 과도상태에 의한 영향을 최소화해야 할 것으로 판단된다. By executing corrosion experiment on Inconel 600, 690 used to material of S/G tube in domestic NPP, this paper show estimation of amount of product such as Co-58, Co-60, Cr-51, Mn-54, Fe-59 which are main exposure cause to the workers in NPP. Therefore, Making the 12 samples consisted of Inconel 600, 690, whole corrosion experiment was carried out for 60 days(each pH by 20 days). The conditions of those tests were similar or more harsh than actual conditions of domestic NPP. The Glow Discharge Spectrometer(GDS) was used for quantitative analysis of results. The results of using GDS, the Inconel 600 corrodes more than Inconel 690 at pH 7 and pH 9. However, it is observed that Inconel 690 corrodes more than Inconel 600 at pH 4. Those results is estimated that test sections had the effect of transient. The long terms of experiment is required to minimize and solve the problem.

      • KCI등재

        액체섬광계수기 교정시 (3)H 선원의 농도 차이에 대한 영향 평가

        염유선 ( Yu Sun Yeom ),한상준 ( Sang Jun Han ),김숭평 ( Soong Pyung Kim ) 조선대학교 공학기술연구원 2010 공학기술논문지 Vol.3 No.4

        This study intends to count environmental samples accurately by liquid scintillation counter[LSC] instrument. For this, (3)H sources of 3,000, 500, 100 disintegration per minute[DPM] were used, and after variables that have an effect on the results of the measurements. A sensitivity study on each variable was performed. Based on the sensitivity study results, optimal counting condition on the counting instrument was deducted, and the effect was evaluated by activity differences. Radioactivity error analysis method was used to verify the calibration data. According to the results of the sensitivity study, Here repeat method and an external source exposure time of 75 sec was used, the measuring accuracy was about 1~3% better than when the existing method was used. According to verification study, The activity difference doesn`t appear nearly. However, because of the effect due to background, noise, etc at activity below of 1,000 DPM, the lower activity, And more error was increased based on these results. And also evaluated accurately the radioactivity of (3)H which can exist into environmental samples around NPP (Nuclear Power Plant). Therefore, it is judged in this paper that a repeat measuring method, irradiating time above 75 sec at least in calibration, and liquid (3)H standard source above 1,000 DPM have to be used.

      • Prevalence of <i>Helicobacter hepaticus</i>, Murine Norovirus, and <i>Pneumocystis carinii</i> and Eradication Efficacy of Cross-Fostering in Genetically Engineered Mice

        YEOM, Su-Cheong,YU, Sun-A,CHOI, Eun-Young,LEE, Byeong-Chun,LEE, Wang-Jae Japanese Association for Laboratory Animal Science 2009 Experimental animals Vol.58 No.5

        <P>We investigated the prevalence of <I>Helicobacter hepaticus</I>, murine norovirus (MNV), and <I>Pneumocystis carinii</I> and the efficacy of cross-fostering for their eradication in 49 genetically engineered mouse (GEM) strains at our institute. Prevalences of <I>H. hepaticus</I>, MNV, and <I>P. carinii</I> were 33.9, 36.5, and 8.6%, respectively, and immunodeficient strains showed relatively higher prevalence of the 3 pathogens than immunocompetent strains. Additionally, the same immune phenotype strains showed similar prevalences. Furthermore, it was found that NKT cells might play a role in <I>H. hepaticus</I> resistance. Interestingly, there was a high incidence of <I>H. hepaticus</I> and MNV multiple infection. Strains with single or multiple infections of <I>H. hepaticus</I>, MNV, and/or <I>P. carinii</I> were selected, and cross-fostering was conducted. Cross-fosterings were successful at eradicating <I>P. carinii</I>, but there were some failures for <I>H. hepaticus</I> and MNV, and the efficacy of eradication was relatively low compared with previous studies. We thought that this low efficacy might have been due to persistent infection and the high suscepibility to <I>H. hepaticus</I> and MNV of immunodeficient GEM strains. Therefore, cross-fostering may be appropriate for <I>P. carinii</I> eradication, but be inappropriate for repopulation of a new breeding colony with <I>H. hepaticus</I> or MNV infected GEM strains. Our findings provide basic data on maintenance, strain susceptibility, and successful rederivation, especially for GEMs.</P>

      • KCI등재

        유기물 발생원에 따른 소독부산물 생성능

        염철민 ( Yeom Cheol Min ),최유식 ( Choe Yu Sig ),조순행 ( Jo Sun Haeng ),윤제용 ( Yun Je Yong ) 한국물환경학회 2003 한국물환경학회지 Vol.19 No.1

        This study was conducted to investigate the characteristics of disinfection by-products formation potential (DBPFPs) in various organic sources. Twenty three different samples were chosen and were divided into three groups; Group 1 (n=14) includes water samples from surface water such as rivers and reservoir, Group 2 (n=5) includes water samples from municipal wastewater treatment plant and primary treatment effluent of night soil, Group 3 (n=4) includes rain water and organics leached from soil and sediment. The type of DBPs investigated were trihalomethanes (THMs), haloacetic acids (HAAS), total organic halides (TOX). Major findings are as follows. First, average SUVA values of most samples were found to be around 2 (ℓ. cm^(-1)/㎎). This indicates that most dissolved organics in surface water and in municipal waste water consist of hydrophilic organic component, supporting the previous report. Second, for most of samples, the range of specific DBPFPs (THMFPs, HAAFPs and TOXFPs)/DOC at 7day incubation existed in the range of 40-60 (average 54) ㎍/㎎ C, 30-120 (average 90) C and 80-250 (average 179) ㎍/㎎ C. respectively. It is noted that THMFPs/DOC and HAAFPs/DOC were found to be relatively higher in dissolved organics from soil samples. Third, DBPs (THMs, HAAs, TOX) in most of samples were increased with time. THMs at 7day incubation increased almost twice compared with that at 3 day incubation. For HAAs and TOXs, despite of the overall increase, some data were found to be decreased with time.

      • KCI등재

        Korean Society of Infectious Diseases/National Evidence-based Healthcare Collaborating Agency Recommendations for Anti-SARS-CoV-2 Monoclonal Antibody Treatment of Patients with COVID-19

        Kim Sun Bean,Kim Jimin,Huh Kyungmin,Choi Won Suk,Kim Yae-Jean,Joo Eun-Jeong,Kim Youn Jeong,Yoon Young Kyung,Heo Jung Yeon,Seo Yu Bin,Jeong Su Jin,Yu Su-Yeon,Peck Kyong Ran,Choi Miyoung,Yeom Joon Sup 대한감염학회 2021 Infection and Chemotherapy Vol.53 No.2

        Neutralizing antibodies targeted at the receptor-binding domain of severe acute respiratory syndrome coronavirus 2 (SARS-CoV-2) spike protein have been developed and now under evaluation in clinical trials. The US Food and Drug Administration currently issued emergency use authorizations for neutralizing monoclonal antibodies in non-hospitalized patients with mild to moderate coronavirus disease 2019 (COVID-19) who are at high risk for progressing to severe disease and/or hospitalization. In terms of this situation, there is an urgent need to investigate the clinical aspects and to develop strategies to deploy them effectively in clinical practice. Here we provide guidance for the use of anti-SARS-CoV-2 monoclonal antibodies for the treatment of COVID-19 based on the latest evidence.

      • KCI등재

        Interim Guidelines on Antiviral Therapy for COVID-19

        Kim Sun Bean,Huh Kyungmin,Heo Jung Yeon,Joo Eun-Jeong,Kim Youn Jeong,Choi Won Suk,Kim Yae-Jean,Seo Yu Bin,Yoon Young Kyung,Ku Nam Su,Jeong Su Jin,Kim Sung-Han,Peck Kyong Ran,Yeom Joon Sup 대한감염학회 2020 Infection and Chemotherapy Vol.52 No.2

        Since the first case was reported in Wuhan, Hubei Province, China on December 12, 2019, Coronavirus disease 2019 (COVID-19) has spread widely to other countries since January 2020. As of April 16, 2020, 10635 confirmed cases have been reported, with 230 deaths in Korea. COVID-19 patients may be asymptomatic or show various clinical manifestations, including acute symptoms such as fever, fatigue, sore throat; pneumonia presenting as acute respiratory distress syndrome; and multiple organ failure. As COVID-19 has such varied clinical manifestations and case fatality rates, no standard antiviral therapy regimen has been established other than supportive therapy. In the present guideline, we aim to introduce potentially helpful antiviral and other drug therapies based on in vivo and in vitro research and clinical experiences from many countries.

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