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송명재(Myung-Jae Song),조효제(Hyo-Jae Jo),김진안(Jin-Ahn Kim),이승건(Seong-Keon Lee) 한국해양공학회 1993 韓國海洋工學會誌 Vol.7 No.2
Responses of marine vehicles and ocean structures in a seaway can be predicted by applying the probabilistic approach. When we consider a linear system, the responses in a random seaway can be evaluated through spectral analysis in the frequency domain. But when we treat nonlinear system in irregular waves, it is necessary to get time history of waves. In the previous study we introduced one-directional waves (long crested waves) as wave environment and carried out calculations and experiments in the waves. But the real sea in which marine vehicles and structures are operated has multi-directional waves (short crested waves). It is important to get a simulated random sea and analyse dynamic problems in the sea. We need entire sample function or probability density function to infer statistical value of random process. However if the process are ergodic process, we can get statistical values by analysis of one sample function. In this paper, we developed the simulation technique of multi-directional waves and proved that the time history given by this method keep ergodic characteristics by the statistical analysis.
극저준위 방사성 폐기물을 위한 효율적인 ${\gamma}$-선 및 ${\beta}$-선 측정 방법 개발
곽성우,염유선,김호경,조규성,박주완,김창락,송명재,Kwak, Sung-Woo,Yeom, Yu-Sun,Kim, Ho-Kyung,Cho, Gyu-Seong,Park, Joo-Wan,Kim, Chang-Lak,Song, Myung-Jae 대한방사선방어학회 2001 방사선방어학회지 Vol.26 No.4
매년 병원에서 사용 후 폐기되는 비가연성 폐기물은 ${\gamma}$-선과 ${\beta}$-선을 방출하지만 방사능은 주변방사능 수준으로 매우 낮다. 이를 측정하기 위한 기존의 방법은 비효율적이고 복잡하므로, 좀더 간단한 방법이 긴요하다. 본 논문에서는 측정 방사선의 특성상 핵종에 따라 다른 측정방법을 사용하였는데, ${\gamma}$-선 방출 핵종은 표준시료로부터 효율곡선식을 도출하여 미지의 방사능을 측정하였다 ${\beta}$-선 방출 핵종은 Monte Carlo 시뮬레이션을 통해 계측 효율을 예측하고 표면장벽형계측기로 측정하여 미지의 방사능 양을 결정하는 새로운 방법을 제시하였다. 연구결과에 의하면 이론적 계산치와 표면장벽형 계측기를 이용하면 전처리를 필요로하는 액체섬광계수기를 이용하지 않고 또한 계측효율을 결정하기 위한 비경제적인 표준시료 측정시험과정 없이도 저에너지 방사선을 약 17% 오차 범위내에서 결정할 수 있다고 판단된다. The non-combustible RI wastes disposed of in hospital every year emit ${\gamma}$-ray or ${\beta}$-ray but their activities are very low to the extent of background. Development of more simple methods is needed because the conventional detection methods are so ineffective and complex. In this study, to solve this problem, detection method using efficiency curve for ${\gamma}$-ray emitting radioactive wastes measurement is proposed and experimental detection efficiency equation is also determined through HPGe's standard specimen measurement. For ${\beta}$-emitting radioisotopes detection, new measurement method using detection efficiency estimated by Monte Carlo simulation and SBD measurements is also proposed. According to the results of this paper, the unknown activity of low-level radioactive wastes without LSC requiring the preparation of standard sample and measurement for standard source detection efficiency could be determined efficiently and simply about ${\pm}17%$ in errors by using the theoretical detection efficiency and the SBD measurement result.
중${\cdot}$저준위 방사성폐기물 유리고화체의 물리${\cdot}$화학적 특성 연구
김천우,박병철,김향미,김태욱,최관식,박종길,신상운,송명재,Kim, Cheon-Woo,Park, Byoung-Chul,Kim, Hyang-Mi,Kim, Tae-Wook,Choi, Kwan-Sik,Park, Jong-Kil,Shin, Sang-Woon,Song, Myung-Jae 한국세라믹학회 2001 한국세라믹학회지 Vol.38 No.9
원자력발전소에서 발생하는 폐수지, 잡고체, 붕산폐액을 유리화 하기 위하여 폐기물별 조성을 바탕으로 유리조성 연구를 수행하였다. 폐수지, 잡고체를 각각 유리화 할 수 있는 두 개 의 후보유리 RG-1과 DG-1 그리고 폐수지, 잡고체, 붕산폐액을 혼합하여 처리할 수 있는 후보유리 MG-1을 개발하였다. 각 후보유리에 대해 운전변수, 고화체 품질, 가용 효과를 평가하였으며 일부 특성들은 실험실적으로 확인하였다. 운전 변수 가운데 유리의 점도와 전기 전도도는 세 후보유리 모두 적정운전 범위값 내에 만족하였으며 밀도, 화학적 견고성, 상안정성 등 고화체의 품질 또한 우수하였다. 개발한 유리 조성 연구를 바탕으로 폐수지, 잡고체, 혼합폐기물을 유리화 할 경우 감용비는 각각 21, 89, 75로 평가되었다. In order to vitrify the Ion-Exchange Resin(IER), Dry Active Waste(DAW), and borate concentrate generated from the commercial nuclear facilities, the glass formulation study based on the their compositions was performed. Two glasses named as RG-1 and DG-1 were formulated as the candidate glasses for the vitrification of hte IER and DAW, respectively. A glass named as MG-1 was also formulated as a candidate glass for the vitrification of the mixed wastes containing the IER, DAW, and borate concentrate. The process parameters, product qualities, and economics were evaluated for the candidate glasses and confirmed experimentally for the some properties. The glass viscosity and electrical conductivity as the process parameters were in the desired ranges. the product qualities such as glass density, chemical durability, phase stability, etc. were satisfactory. In case of vitrifying the wastes using our developed glass formulation study, the volume reduction factors for the IER, DAW and mixed wastes were evaluated as 21, 89 and 75, respectively.
갑상선암 환자에 대한 방사선옥소 치료시 물리적 선량 측정
고창순(Chang Soon Koh),이명철(Myung Chul Lee),김종순(Chong Soon Kim),김희근(Hee Geun Kim),강덕원(Duck Won Kang),송명재(Myung Jae Song),김명선(Myung Seon Kim),정내인(Nae In Jeong),이재용(Jai Yong Lee),김종호(Chong Ho Kim) 대한핵의학회 1994 핵의학 분자영상 Vol.28 No.1
N/A Radioactive iodine has been widely used in patients with thyroid cancer combined with surgical treatment. However, due to individual variations in absorption and excretion and uptake by tumor tissue of radioactive iodine, there are differences in therapeutic effect and adverse effects even if the same doses are administrated. So this study compared the therapeutic effect and radiation hazard by measuring internal radiation dose. Of total 27 patients with well differentiated thyroid cancer who had been thyroidectomized, we administered radioactive iodine 100 mCi, 150 mCi, 200 mCi. According to BEL DOSIMETRY PROTOCOL, beta and gamma ray dose were estimated from a polt of the logarithrn of the percent of dose per liter of whole blood versus day, and percent dose retained versus day using semilogarithmic paper, respectivel y. 1) Physical dose to whole blood averaged 56.54+13.02 rad in 100 mCi administered group, 76.83+ 19.97 rad in 150 mCi administered group, 95.08 +- 25.51 rad in 200 mCi administered group and there has been a significant correlation among the groups. 2) Mean percent dose retained 48 hours later was 26.34%. 3) There was no significant correlation of physical dose between absence and presence of metastasis. 4) l7 of 19 patients who has been followed up with TSH and serum throglobulin, Thallium scan were successfully ablated by radioactive iodine. 5) Leukocyte, lymphocyte, neutrophil, platelet counts all declined in 4-6 weeks and most of all were restored 3 months 1ater. 6) There was no significant correlation between physical dosimetry and biologic dosimetry. Generally administered doses of radioactive iodine (100-200 mCi) to patients with thyroid cancer postoperatively had developed transient bone marrow suppression and minimal chromosomal aberration, but they were within safety dose to blood (200 rad). And there has been no significant differences in residual dose 48 hours later between Korean and western people.
강희석,이한수,정흥석,안도희,손순환,정양근,송명재 ( Hee Suk Kang,Han Soo Lee,Hongsuk Chung,Do Hee Ahn,Soon Hwan Son,Yang Geun Chung,Myung Jae Song ) 한국공업화학회 1996 공업화학 Vol.7 No.4
중수형 발전소에서 삼중수소 제거 공정에 이용되는 소수성 고분자촉매의 담체인 스티렌-디비닐벤젠 공중합체의 제조 특성을 실험하였다. 스티렌-디비닐벤젠 고분자담체의 제조시 담체의 표면 특성에 대한 용매의 영향을 고찰하기 위하여 일정한 용매계에서 용매비를 변화시켜 solvating power 값을 구하였다. 거시기공 형태의 담체가 제조되기 위한 solvating power는 가교도가 20%일 때 3 이상, 가교도가 40%일 때는 1 이상의 값이 필요하였으며 약 40℃에서 2시간 이상 용액의 안정이 필요하였다. 또한 후처리 방법은 담체를 건조시키기 전에 용매를 제거하는 방법이 가장 우수한 기공 특성을 나타내었다. 담체의 입자 크기는 교반속도 및 계면활성제의 농도가 낮을수록 더 크게 생성됨을 알 수 있었다. This study represents the synthetic characteristics of styrene-DVB copolymer which is used as a catalyst support for the removal of tritium in CANDU. To evaluate the effect of solvent on the styrene-DVB polymeric support, the solvating power dependent on various kinds and composition of solvents was calculated. In order to synthesize the macroreticular type polymer bead, the following conditions are needed; solvating power should be higher than 1 for 20% of crosslinkage and higher than 3 for 40% of crosslinkage. Stabilization of organic monomers at about 40℃ for more than 2 hours is prerequisite. Removal of solvent prior to drying is preferred for the post-treatment of the bead. The polymer particle size was increased by lowering concentration of surfactant and stirring speed.
전혈 , 림프구와 백혈구 연층 각각의 방사성 동위원소 체외 조사후 배양을 이용한 생물학적 선량측정
김종호,이동수,최창운,정준기,이명철,고창순,김종순,김희근,강덕원,송명재 ( Jong Ho Kim,Dong Soo Lee,Chang Woon Choi,June Key Chung,Myung Chul Lee,Chang Soon Koh,Chong Soon Kim,Hee Geun Kim,Duck Won Kang,Myung Jae Song ) 대한핵의학회 1995 핵의학 분자영상 Vol.29 No.1
The purpose of this study was to establish mononuclear cell cultures such as lymphocytes or buffy coat for the biological dosimetry of in vitro irradiation of the radionuclide Tc 99m in order to exclude the effect of residual doses seen in the cultures of whole blood. Biological dosimetry of Tc-99m on cultured mononuclear cells at doses ranging from 0.05 to 6.00 Gy, by scoring unstable chromosomal aberrations(Ydr) observed in cultured lymphocytes, were performed using peripheral venous blood of healthy normal person. The results showed that; (1) Jn vitro irradiation of radioisotope in separated lymphocyte or buffy coat showed trace amount af residual doses of isotope after washing. Residual doses of isotopes are increased in proportion tn exposed time and irradiated dose without difference between I-131 anct Tc 99m. (2) We obtained these linear-quadratic dose response equations in lymphocyte and buffy coat culture after in vitro irradiation of Tc-99m, respectively (Ydr = 0,001949 D+ 0,006279B+ 0.000185; Ydr= 0.002531 D 0.003274 D+0.003488). In aonclusion, the linear quadrstic dose response equation from in vitro irradiation of Tc 99m with lymphocyte and buffy coat culture was thought to be useful for assessing Tc 99m indueed biological effects. And mononuclear cell cultures seem to be the most appropriate experimental rnodel for the assessment of biological dosimetry of internal irradiation of radionuclides.
방사성옥소 투여에 따른 말초혈액 림프구 수의 변화 및 염색체이상 빈도의 관찰
김종순(Chong Soon Kim),한승수(Seung Soo Han),김희근(Hee Geun Kim),강덕원(Duck Won Kang),송명재(Myung Jae Song),구천희(Chun Hee Koo),신민호(Min Ho Shin),박영주(Young Ju Park),이정임(Jung Yim Lee),박태용(Tae Yong Park),이재용(Jae Yong 대한핵의학회 1995 핵의학 분자영상 Vol.29 No.3
N/A Background: For biological dosimetry of radiation exposure, both observing hema-tologic change and calculating Ydr by chromgsomal analysis as biological indicators are widely used. However, due to the lack of studies on biological dosimetry of radiation dose absorbed in the body such as in the cases of radioactive iodine therapy, the maximal and safe dose is not well known, nor is the extent to which the body can safely endure radiation exposure. Purpose: To investegate the practical applicability of hematologic changes and Ydr as an indicator for estimating radiation exposure, to patients with thyroid diseases after doses of radioactive iodine. Material and Methods: 5 patients with hyperthyroidism and 35 patients who have had thyroid cancer operation were under treatment with radioactive iodine, changes in number of lymphocytes were tracked and Ydr was calculated for more than 2 months by chromosomal analysis in peripheral lymphocytes. Results: 1) The number of lymphocytes began to decrease 2 weeks after doses of radioactive iodine, and reached the nadir after 6 and 8 weeks, then gradually recovered. 2) The nadir count of lymphocytes was reversely correlated with the administered dosage of radioactive iodine. 3) Ydr was generally stable between 2 and 8 weeks. 4) The maximal value of Ydr was correlated with the administered dosage of radioactive iodine. 5) Ydr value at the 2nd week increased with augmented dosage of radioactive iodine. 6) Ydr value at the 2nd week was correlated with fall of lymphocyte count. Conclusion: Patients must be closely observed, because temporary bone marrow suppression and slight chromosomal aberration can be produced by even generally used dosages of radioactive iodine for diagnosis and therapy. Maximal percent fall of lymphocyte count, Ydr at the 2 week interval and maximal Ydr can be used as the biological predictor of administered dosage of radioactive iodine.