• 제목/요약/키워드: radioactive Co

검색결과 564건 처리시간 0.026초

일부 제조업 사업장의 사무 및 공장동에서의 라돈농도 수준 및 유효선량 평가 (Evaluation of Effective Dose and Exposure Levels of Radon in Office and Plant Buildings)

  • 정은교;김기웅
    • 한국산업보건학회지
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    • 제27권1호
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    • pp.38-45
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    • 2017
  • Objectives: Radon may be second only to smoking as a cause of lung cancer. Radon is a colorless, tasteless radioactive gas that is formed via the radioactive decay of radium. Therefore, radon levels can build up based on the amount of radium contained in construction materials such as phospho-gypsum board or when ventilation rates are low. This study provides our findings from evaluation of radon gas at facilities and offices in an industrial complex. Methods: We evaluated the office rooms and processes of 12 manufacturing factories from May 14, 2014 to September 23, 2014. Short-term data were measured by using real-time monitoring detectors(Model 1030, Sun Nuclear Co., USA) indoors in the office buildings. The radon measurements were recorded at 30-minute intervals over approximately 48 hours. The limit of detection of this instrument is $3.7Bq/m^3$. Also, long-term data were measured by using ${\alpha}-track$ radon detectors(${\alpha}-track$, Rn-tech Co., Korea) in the office and factory buildings. Our detectors were exposed for over 90 days, resulting in a minimum detectable concentration of $7.4Bq/m^3$. Detectors were placed 150-220 cm above the floor. Results: Radon concentrations averaged $20.6{\pm}17.0Bq/m^3$($3.7-115.8Bq/m^3$) in the overall area. The monthly mean concentration of radon by building materials were in the order of gypsum>concrete>cement. Radon concentrations were measured using ${\alpha}-track$ in parallel with direct-reading radon detectors and the two metric methods for radon monitoring were compared. A t-test for the two sampling methods showed that there is no difference between the average radon concentrations(p<0.05). Most of the office buildings did not have central air-conditioning, but several rooms had window- or ceiling-mounted units. Employees could also open windows. The first, second and third floors were used mainly for office work. Conclusions: Radon levels measured during this assessment in the office rooms of buildings and processes in factories were well below the ICRP reference level of $1,000Bq/m^3$ for workplaces and also below the lower USEPA residential guideline of $148Bq/m^3$. The range of indoor annual effective dose due to radon exposure for workers working in the office and factory buildings was 0.01 to 1.45 mSv/yr. Construction materials such as phospho-gypsum board, concrete and cement were the main emission sources for workers' exposure.

탈수 작용에 따른 몬모릴로나이트의 코발트 흡착 특성 변화 (Changes in Cobalt Adsorption Properties of Montmorillonite by Dehydration)

  • 장영준;김영규
    • 광물과 암석
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    • 제36권2호
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    • pp.107-115
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    • 2023
  • 코발트는 합금산업에서 발생되는 산업 폐기물과 산성광산배수로 자연에 유입될 수 있으며 또한 고준위 방사성 폐기물을 구성하는 방사성 핵종(60Co)기도 하다. 스멕타이트는 이들을 흡착 격리하는데 유용하게 사용될 수 있는 광물이다. 본 연구에서는 기존에 특성이 잘 알려진 스멕타이트 중 The Clay Mineral Society (CMS)의 source clay인 Cheto-type montmorillonite (Cheto-MM)를 사용하여 가열에 의한 탈수 전후 광물의 층간수 존재 여부에 따른 흡착 자리가 코발트 흡착에 미치는 영향을 평가하고, 흡착 속도 및 등온흡착식 모델을 적용하여 Cheto-MM의 코발트에 대한 흡착 기작을 연구하였다. 본 연구 결과 탈수 및 이에 따른 층간 수축에 의해 흡착 특성이 달라지는 것을 확인할 수 있었으며, 코발트는 Cheto-MM의 층 모서리 자리에서의 흡착이 약 38%, 층간 내부에서의 흡착이 약 62%를 차지하는 것으로 확인되었고 Cheto-MM의 코발트 흡착은 층간 내부에 의한 영향이 큰 것으로 판단된다. 이러한 흡착에 있어 흡착 속도 모델을 적용한 결과, Cheto-MM의 코발트 흡착 속도는 pseudo-second-order 모델로 설명되며 농도에 따른 흡착은 Langmuir 등온흡착 모델로 가장 잘 설명되었다. 본 연구는 몬모릴로나이트의 흡착 자리에 따른 코발트의 흡착 양상에 대한 기본지식을 제공하고, 추후 고준위 방사성 폐기물 처분장에서의 스멕타이트의 흡착 거동을 예측하는데 유용하게 사용될 수 있을 것으로 생각된다.

$(Zr-DEHPA)/n-dodecane-HNO_3$ 금속함유 추출 계에 의한 악티나이드(III)및 RE의 공추출 및 상호 분리 (Evaluation of co- and Mutual Weparation for Actinide(III) and RE by a $(Zr-DEHPA)/n-dodecane-HNO_3$ Extraction System)

  • 이일희;임재관;정동용;양한범;김광욱
    • 방사성폐기물학회지
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    • 제5권2호
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    • pp.123-132
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    • 2007
  • 본 연구는 실제 HLW 수준의 다성분 계 모의 용액으로부터 $Zr-DEHPA/NDD-HWO_3$ 금속함유 추출 계에 의한 Am-Cm/RE 원소의 공분리 및 이의 상호분리 연구를 수행하였다. 우선 금속함유 추출제인 Zr-DEHPA를 자체 제조하고, 제 3상 방지 조건 결정과 질산 농도, DEHPA 농도, Zr 함유량 등이 공추출에 미치는 영향을 평가하여 최적 조건으로 (15g/L Zr-1M DEHPA)/NDD-1M $HNO_3$ 추출 계를 설정하였다. 이때 추출률은 Am (81%), Cm (85%), RE 원소 (80% 이상), Mo (98%), Fe (85%), U (98%), Np (73%), 기타 원소 (5% 이하) 등으로 Am-Cm/RE의 공분리 적용성은 양호하나, U, Np, Mo, Fe의 선제거가 필요하고 특히 제 3상 형성 유발 물질인 Zr이 거의 함유되지 않아야 한다. 그리고 공추출된 Am-Cm/RE를 Am-Cm (역추출제 : 0.05M DTPA-1M Lactic acid-pH 3.6)${\rightarrow}RE$ (역추출제 : 5M $HNO_3$) 순으로 상호 분리하여 각각의 분리계수를 평가하였으며 이때 Am은 65.4%, Cm은 63.9% RE 원소(Y 제외)는 85% 이상이 역추출 되었다.

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염화칼리와 석회의 동시살포가 주요 작물의 생육중에 침적한 $^{54}Mn,\;^{60}Co,\;^{85}Sr\;and\;^{137}Cs$의 뿌리흡수에 미치는 영향 (Effects of KCl and Lime Application on Root Uptake of $^{54}Mn,\;^{60}Co,\;^{85}Sr\;and\;^{137}Cs$ Deposited during Growth of Major Crop Plants)

  • 최용호;조재성;이명호;최근식;이정호
    • Journal of Radiation Protection and Research
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    • 제20권4호
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    • pp.245-253
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    • 1995
  • 2년 간의 온실실험을 통하여 벼, 콩, 배추, 무의 생육초기에 $^{54}Mn,\;^{60}Co,\;^{85}Sr\;and\;^{137}Cs$의 혼합용액을 산성 양질사토로 상층부를 채운 재배강자내 담수 또는 토양의 표면에 가한 후 비료용 염화칼리와 소석회를 각각 $m^2$당 200g 및 83g 수준으로 동시에 처리하고 흡수억제 효과를 조사하였다. 칼리와 석회 처리시 각 핵종의 작물체 부위간 농도분포 및 작물에 따른 흡수양상의 변화는 대체로 무처리시와 비슷한 경향이었다. 토양-작물체간 핵종의 전이계수는 칼리와 석회 처리에 의해 벼에서는 $^{85}Sr$$^{137}Cs$, 배추에서는 네 핵종 모두, 무에서는 $^{54}Mn,\;^{60}Co,\;and\;^{137}Cs$의 경우 생육장해 없이 왜 크게 감소하였으나 이밖의 경우에는 감소효과를 인정할 수 없었다. 벼에서 전이계수의 감소 정도는 $^{85}Sr$가 60% 정도로 가장 컸고 배추와 무에서는 $^{54}Mn$가 80% 정도로 가장 컸다. 본 연구결과는 작물 생육중 농경지의 방사능 오염시 대책 수립을 위한 기초정보로 이용될 수 있다.

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한국원자력 연구소 실증소각시설에서의 저준위방사성폐기물 시험소각 (Trial Burns of Low-Level Radioactive Wastes the Demonstration-Scale Incineration Plant at KAERI)

  • Yang, Hee-Chul;Kim, In-Tae;Kim, Jeong-Guk;Kim, Joon-Hyung;Seo, Yong-Chil
    • Nuclear Engineering and Technology
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    • 제27권5호
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    • pp.767-774
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    • 1995
  • 방사성 동위원소 추적자를 포함한 모의폐기물의 시험소각을 통하여 $^{60}$Co, $^{54}$Mn 및 $^{137}$Cs의 소각공정에서의 거동을 고찰하였다. 공정 내에서 비휘발성 방사성 핵종들인 $^{60}$Co 및 $^{54}$Mn의 거동은 입자상 물질의 거동과 유사하였다. $^{60}$Co 및 $^{54}$Mn의 제염계수(DF) 는 각각 4.7$\times$$10^{5}$ 및 6.2$\times$$10^{5}$ 이었다. 반휘발성인 핵종의 거동은 소각온도의 의존성을 보여주었다. 반휘발성 $^{137}$Cs의 제염계수는 85$0^{\circ}C$$700^{\circ}C$ 의 다른 소각온도에서 각각 2.8$\times$$10^3$, 2.6$\times$$10^4$이었다. 원자력 발전소(NPS) 고리 3, 4호 기에서 운반된 건조 방사성폐기물(DAW)에 대한 시험소각도 실시하였다. 폐기물에 포함된 총 베타 /감마 방사능에 대한 제염계수가 1.1$\times$$10^{5}$ 이었다. 앞의 추적자 시험의 결과 및 건조 고체폐기물 내 핵종분포에 기준을 둔 예상제염계수보다 다소 높은 값을 보였다. 굴뚝에서의 배출농도는 0.019 Bq /N $m^3$으로 기체상 배출물에 대한 최대허용농도(MPC)를 만족시킬 수 있었다.

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A Comparative Study on Effective One-Group Cross-Sections of ORIGEN and FISPACT to Calculate Nuclide Inventory for Decommissioning Nuclear Power Plant

  • Cha, Gilyong;Kim, Soonyoung;Lee, Minhye;Kim, Minchul;Kim, Hyunmin
    • Journal of Radiation Protection and Research
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    • 제47권2호
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    • pp.99-106
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    • 2022
  • Background: The radionuclide inventory calculation codes such as ORIGEN and FISPACT collapse neutron reaction libraries with energy spectra and generate an effective one-group cross-section. Since the nuclear cross-section data, energy group (g) structure, and other input details used by the two codes are different, there may be differences in each code's activation inventory calculation results. In this study, the calculation results of neutron-induced activation inventory using ORIGEN and FISPACT were compared and analyzed regarding radioactive waste classification and worker exposure during nuclear decommissioning. Materials and Methods: Two neutron spectra were used to obtain the comparison results: Watt fission spectrum and thermalized energy spectrum. The effective one-group cross-sections were generated for each type of energy group structure provided in ORIGEN and FISPACT. Then, the effective one-group cross-sections were analyzed by focusing on 59Ni, 63Ni, 94Nb, 60Co, 152Eu, and 154Eu, which are the main radionuclides of stainless steel, carbon steel, zircalloy, and concrete for decommissioning nuclear power plant (NPP). Results and Discussion: As a result of the analysis, 154Eu and 59Ni may be overestimated or underestimated depending on the code selection by up to 30%, because the cross-section library used for each code is different. When ORIGEN-44g, -49g, and -238g structures are selected, the differences of the calculation results of effective one-group cross-section according to group structure selection were less than 1% for the six nuclides applied in this study, and when FISPACT-69g, -172g, and -315g were applied, the difference was less than 1%, too. Conclusion: ORIGEN and FISPACT codes can be applied to activation calculations with their own built-in energy group structures for decommissioning NPP. Since the differences in calculation results may occur depending on the selection of codes and energy group structures, it is appropriate to properly select the energy group structure according to the accuracy required in the calculation and the characteristics of the problem.

Simulation analysis and evaluation of decontamination effect of different abrasive jet process parameters on radioactively contaminated metal

  • Lin Zhong;Jian Deng;Zhe-wen Zuo;Can-yu Huang;Bo Chen;Lin Lei;Ze-yong Lei;Jie-heng Lei;Mu Zhao;Yun-fei Hua
    • Nuclear Engineering and Technology
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    • 제55권11호
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    • pp.3940-3955
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    • 2023
  • A new method of numerical simulating prediction and decontamination effect evaluation for abrasive jet decontamination to radioactively contaminated metal is proposed. Based on the Computational Fluid Dynamics and Discrete Element Model (CFD-DEM) coupled simulation model, the motion patterns and distribution of abrasives can be predicted, and the decontamination effect can be evaluated by image processing and recognition technology. The impact of three key parameters (impact distance, inlet pressure, abrasive mass flow rate) on the decontamination effect is revealed. Moreover, here are experiments of reliability verification to decontamination effect and numerical simulation methods that has been conducted. The results show that: 60Co and other homogeneous solid solution radioactive pollutants can be removed by abrasive jet, and the average removal rate of Co exceeds 80%. It is reliable for the proposed numerical simulation and evaluation method because of the well goodness of fit between predicted value and actual values: The predicted values and actual values of the abrasive distribution diameter are Ф57 and Ф55; the total coverage rate is 26.42% and 23.50%; the average impact velocity is 81.73 m/s and 78.00 m/s. Further analysis shows that the impact distance has a significant impact on the distribution of abrasive particles on the target surface, the coverage rate of the core area increases at first, and then decreases with the increase of the impact distance of the nozzle, which reach a maximum of 14.44% at 300 mm. It is recommended to set the impact distance around 300 mm, because at this time the core area coverage of the abrasive is the largest and the impact velocity is stable at the highest speed of 81.94 m/s. The impact of the nozzle inlet pressure on the decontamination effect mainly affects the impact kinetic energy of the abrasive and has little impact on the distribution. The greater the inlet pressure, the greater the impact kinetic energy, and the stronger the decontamination ability of the abrasive. But in return, the energy consumption is higher, too. For the decontamination of radioactively contaminated metals, it is recommended to set the inlet pressure of the nozzle at around 0.6 MPa. Because most of the Co elements can be removed under this pressure. Increasing the mass and flow of abrasives appropriately can enhance the decontamination effectiveness. The total mass of abrasives per unit decontamination area is suggested to be 50 g because the core area coverage rate of the abrasive is relatively large under this condition; and the nozzle wear extent is acceptable.

옥천대(沃川帶) 우라늄광층(鑛層)의 구조규제(構造規制) 및 지구화학적(地球化學的) 특성연구(特性硏究) (Lithologic and Structural Controls and Geochemistry of Uranium Deposition in the Ogcheon Black-Slate Formation)

  • 이대성;윤석규;이종혁;김정택
    • 자원환경지질
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    • 제19권spc호
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    • pp.19-41
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    • 1986
  • Structural, radioactive, petrological, petrochemical, mineralogical and stable isotopic study as well as the review of previous studies of the uranium-bearing slates in the Ogcheon sequence were carried out to examine the lithological and structural controls, and geochemical environment in the uranium deposition in the sequence. And the study was extended to the coal-bearing formation (Jangseong Series-Permian) to compare the geochemical and sedimentologic aspects of uranium chemistry between Ogcheon and Hambaegsan areas. The results obtained are as follows: 1. The uranium mineralization occurs in the carbonaceous black slates of the middle to lower Guryongsan formation and its equivalents in the Ogcheon sequence. In general, two or three uranium-bearing carbonaceous beds are found with about 1 to 1.5km stratigraphic interval and they extend from Chungju to Jinsan for 90km in distance, with intermittent igneous intrusions and structural Jisturbances. Average thickness of the beds ranges from 20 to 1,500m. 2. These carbonaceous slate beds were folded by a strong $F_1$-fold and were refolded by subsequent $F_1$-fold, nearly co-axial with the $F_1$, resulting in a repeated occurrence of similar slate. The carbonaceous beds were swelled in hing zones and were shrinked or thined out in limb by the these foldings. Minor faulting and brecciation of the carbonaceous beds were followed causing metamorphism of these beds and secondary migration and alteration of uranium minerals and their close associations. 3. Uranium-rich zones with high radioactive anomalies are found in Chungju, Deogpyong-Yongyuri, MiwonBoun, Daejeon-Geumsan areas in the range of 500~3,700 cps (corresponds to 0.017~0.087%U). These zones continue along strike of the beds for several tens to a few hundred meters but also discontinue with swelling and pinches at places that should be analogously developed toward underground in their vertical extentions. The drilling surveyings in those area, more than 120 holes, indicate that the depth-frequency to uranium rich bed ranging 40~160 meter is greater. 4. The features that higher radioactive anomalies occur particularly from the carbonaceous beds among the argillaceous lithologic units, are well demonstrated on the cross sections of the lithology and radioactive values of the major uranium deposits in the Ogcheon zone. However, one anomalous radioactive zone is found in a l:ornfels bed in Samgoe, near Daejeon city. This is interpreted as a thermal metamorphic effect by which original uranium contents in the underlying black slate were migrated into the hornfels bed. 5. Principal minerals of the uranium-bearing black slates are quartz, sericite, biotite and chlorite, and as to chemical composition of the black slates, $Al_2O_3$ contents appear to be much lower than the average values by its clarke suggesting that the Changri basin has rather proximal to its source area. 6. The uranium-bearing carbonaceous beds contain minor amounts of phosphorite minerals, pyrite, pyrrhotite and other sulfides but not contain iron oxides. Vanadium. Molybdenum, Barium, Nickel, Zirconium, Lead, Cromium and fixed Carbon, and some other heavy metals appear to be positive by correlative with uranium in their concentrations, suggesting a possibility of their genetic relationships. The estimated pH and Eh of the slate suggests an euxenic marine to organic-rich saline water environment during uranium was deposited in the middle part of Ogcheon zone. 7. The Carboniferous shale of Jangseong Series(Sadong Series) of Permian in Hambaegsan area having low radioactivity and in fluvial to beach deposits is entirely different in geochemical property and depositional environment from the middle part of Ogcheon zone, so-called "Pibanryong-Type Ogcheon Zone". 8. Synthesizing various data obtained by several aspects of research on uranium mineralization in the studied sequence, it is concluded that the processes of uranium deposition were incorporated with rich organic precipitation by which soluble uranyl ions, $U{_2}^{+{+}}$ were organochemically complexed and carried down to the pre-Ogcheon sea bottoms formed in transitional environment, from Red Sea type basin to Black Sea type basin. Decomposition of the organic matter under reducing conditions to hydrogen sulfide, which reduced the $UO{_2}^{+2}$ ions to the insoluble uranium dioxide($UO_2$), on the other side the heavy metals are precipitated as sulfides. 9. The EPMA study on the identification of uraninite and others and the genetic interpretation of uranium bearing slates by isotopic values of this work are given separately by Yun, S. in 1984.

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$(TBP-TOA)/n-dodecane-HNO_3$ 추출 계에 의한 Tc, Np, U의 공추출 및 순차분리 평가 (Evaluation of co- and Sequential Separation for Tc, Np and U by a $(TBP-TOA)/n-dodecane-HNO_3$ Extraction System)

  • 이일희;임재관;정동용;양한범;김광욱
    • 방사성폐기물학회지
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    • 제5권2호
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    • pp.133-143
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    • 2007
  • 본 연구에서는 다성분의 모의 HLW 용액으로부터 $(TBP-TOA)/NDD-HNO_3$ 혼합추출 계에 의한 Tc, Np, U의 공분리 및 이의 순차 분리 적용 가능성을 평가하였다. 우선 제 3상 방지 및 TBP, TOA,질산 농도 등이 Tc, Np, U의 공분리에 미치는 영향 등을 고려하여 최적 조건으로 (30% TBP-0.5% TOA)/NDD-1M $HNO_3$ 계를 선정하였다. 이때 추출율은 Tc (81%), Np (85%), U (93%), Am/RE 원소 (9% 이하) Pd (약 8%), 기타 원소 (5% 이하)로 Tc, Np 및 U의 공분리는 매우 우수하였으나, 조업 측면에서 Zr의 선 제거 (약 99 % 이상)가 요구되었다. 그리고 공추출된 Tc, Np 및 U을 Tc (역추출제 : 5 M $HNO_3$)${\rightarrow}Np$ 환원 (역추출제 : 0.1 M AHA)${\rightarrow}U$ (역추출제 : 0.01 M $HNO_3$)의 순으로 순차 분리하여 각각의 분리계수를 평가하였으며, 이때 Tc은 95%, Np은 98%, U은 99%를 회수할 수 있었다.

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제염제의 $^{137}Cs$$^{60}Co$에 의한 피부오염의 제염효과에 관한 연구 (Study on the Effectiveness of some Decontamination Agents against Skin Contamination of $^{137}Cs$ and $^{60}Co$)

  • 전제근;지평국;곽상수;김병태;박종묵
    • Journal of Radiation Protection and Research
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    • 제23권1호
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    • pp.7-15
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    • 1998
  • 몇 종류의 제염제에 대한 제염효과를 평가하기 위해 $^{60}Co$$^{137}Cs$에 의한 피부오염의 제염실험을 수행하였다. 본 연구에서는 인체피부 대신에 돼지피부를 활용하였으며, 피부오염용액으로는 $^{60}CoCl_2$$^{137}CsCl$ 용액을 사용하였다. 그리고 제염제로는 현재 사용되고 있는 비눗물, EDTA 외에 오염된 구조물의 표면오염 제거를 위해 원자력연구소에서 개발한 KAERICON과 본 연구를 통해 제조한 IOCON, TRICON 및 CHARCON 등을 이용하여 피부오염에 대한 제염을 실시하여 각 제염제의 제염효과를 평가하였다. 방사성물질의 피부침투정도를 파악하기 위하여 16시간동안 방사성물질을 시료표면에 점착시킨 후 감마선 측정을 통해 침투율을 평가하였으며, 이 실험에서 $^{137}Cs$의 경우 11.5%, $^{60}Co$의 경우 3.2% 정도가 피부로 침투됨을 알 수 있었다. 각 제염제의 제염효과를 평가해본 결과 KAERICON은 $^{137}Cs$에 대하여 최고 52.1%(제염계수 2.1)의 제염율을 나타내었으며, IOCON도 $^{137}Cs$에 대하여 비교적 좋은 제염율(제염계수 1.9)을 나타내었다. 그러나 $^{60}Co$에 대해서는 IOCON, CHARCON 모두 20%(제염계수 1.2) 미만의 제염율을 나타내었으며, KAERICON도 $^{60}Co$에 대해 낮은 제염율(제염계수 1.1)을 나타내었다. TRICON은 $^{137}Cs$에 대해 $1.6{\sim}1.8$의 제염계수를 나타내었으며, $^{60}Co$에 대해서는 $1.0{\sim}1.2$의 제염계수를 나타내었다.

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