• 대한핵의학회지
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• 제19권2호
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• pp.93-95
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• 1985

A simple imaging procedure has been devised for patients with peritoneo-venous shunts when ascites reaccumulates and a decision must be made on whether or not to revise the shunt. We recently experienced a patient with reaccumulated ascites in whom obstruction of peritoneo-venous shunt was suspected. 5 mCi of $^{99m}Tc-phytate$ was injected into the peritoneal cavity and imaging of the abdomen was performed $1\sim30$ minutes later. With a proper funtioning shunt, radioactivity in the liver and spleen were easily identifiable in this case. If the shunt is obstructed, tracer activity will remain in the peritoneal cavity and thus can not be identifiable in the liver or spleen. Conclusively, radionuclide methods might be very useful for evaluation of peritoneo-venous shunt patency.

• Nuclear Engineering and Technology
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• 제51권4호
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• pp.1176-1179
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• 2019

Measurements of activity concentrations of radionuclides in atmospheric releases were performed in 2017-2018 at vent stacks of seven Russian nuclear power plants. The selected instruments and research methods, with detection limits significantly lower than the existing detection limit of Russian NPPs routine control, allowed to reliably determine up to 26 radionuclides. Analysis of experimental data allows to determine the list of radionuclides for calculation the effective dose rates to public and the permissible annual discharge levels for each Russian NPP. Radiocarbon is determined as major contributor for the dose from the atmospheric releases of LWGR reactors - up to 98% for EGP-6 and RBMK-1000 (Smolensk NPP) reactors. For PWR reactors (VVER) radionuclides contribution to the annual dose from atmospheric releases is more complicated, but, in general, dose is formed by tritium, $^{14}C$ and noble gases. The special monitoring results with ranking of measured radionuclides according to their contribution to the effective dose makes it possible to optimize the list of controlled radionuclides in airborne releases of Russian NPPs from 94 to 8-16 for different NPPs.

• Nuclear Engineering and Technology
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• 제55권5호
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• pp.1871-1877
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• 2023

The main goal of the coordinated project development of therapeutic radiopharmaceuticals of Y-90 and Re-188 is to exploit advancements in radionuclide production technology. Here, direct and indirect production methods with medium reactor and cyclotron are compared to evaluate derived neutron flux and production yield. First, nano-sized ¹⁸⁶W and ⁸⁹Y specimens are suspended in water in a quartz vial by FLUKA simulation. Then, the solution is irradiated for 4 days under 9E+14 n/cm2/s neutron flux of reactor. Also, a neutron activator including three layers-lead moderator, graphite reflector, and polyethylene absorbent- is simulated and tungsten target is irradiated by 60 MeV protons of cyclotron to generate induced neutrons for ¹⁸⁸W and ⁹⁰Sr production via neutron capture. As the neutron energy reduced, the flux gradually increased towards epithermal range to satisfy (n/2n,γ) reactions. The obtained specific activities at saturation were higher than the reported experimental values because the accumulated epithermal flux and nano-sized specimens influence the outcomes. The beta emitters, which are widely utilized in brachytherapy, appeal an alternative route to locally achieve a rational yield. Therefore, the proposed method via neutron activator may ascertain these broad requirements.

• Journal of Radiation Protection and Research
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• 제44권2호
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• pp.79-88
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• 2019

Background: The main goal of experiments is to compare various operational and technical characteristics of D-Shuttle semiconductor personal dosimeters of the Japanese company "Chiyoda Technol Corporation" and Harshaw thermoluminescent dosimeters (TLD) manufactured by "Thermo Fisher Scientific" and DTL-02 of the Russian Research and Production Enterprise (RPE) "Doza" by their occupational and calibration exposure at various dose equivalents from 0.5 to 20 mSv of gamma-radiation. Materials and Methods: Besides dosimeters DTL-02, D-Shuttle and Harshaw TLD, there were also used: (1) the primary reference radionuclide source Hopewell Designs IAEA: G10-1-12 with $^{137}Cs$ isotope (an error is not more than 6% and activity is 20 Ci), and (2) the verification device UPGD-2M of RPE "Doza" and installed in the National Center for Expertise and Certification of the Republic of Kazakhstan (Kapchagai, the National Center for Expertise and Certification). Results and Discussion: The main results of researches are the following: (1) TLDs for Harshaw 6600 and DVG-02TM have an approximately equal measurement accuracy of the individual dose equivalents in the range from 0.5 to 20 mSv of gamma-radiation. (2) Advantages of dosimeters for Harshaw 6600 are due to the high measurement productivity and opportunity to indicate the dose on the skin $H_p$(0.07). Advantages of DVG-02TM consist of operation simplicity and lower cost than of Harshaw 6600. (3) D-Shuttles are convenient for use in the current and the operational monitoring of ionizing radiation. Measurement accuracy and 10% linearity of measurements are ensured when D-Shuttle is irradiated with dose equivalents below 1 mSv at the equivalent dose rate not higher than $3mSv{\cdot}hr^{-1}$. This allows using D-Shuttle at a routine technological activity. Conclusion: The obtained results of experiments demonstrate advantages and disadvantages of D-Shuttle semiconductor dosimeters in comparison with two TLD systems of DVG-02TM and Harshaw 6600.

• Nuclear Engineering and Technology
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• 제53권4호
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• pp.1210-1217
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• 2021

The analysis of ⁴¹Ca in concrete generated from the nuclear facilities decommissioning is critical for ensuring the safe management of radioactive waste. An analytical method for the determination of ⁴¹Ca in concrete is described. ⁴¹Ca is a neutron-activated long radionuclide, and hence, for accurate analysis, it is necessary to completely extract Ca from the concrete sample where it exists as the predominant element. The decomposition methods employed were the acid leaching, microwave digestion, and alkali fusion. A comparison of the results indicated that the alkali fusion is the most suitable way for the separation of Ca from the concrete sample. Several processes of hydroxide and carbonate precipitation were employed to separate ⁴¹Ca from interferences. The method relies on the differences in the solubility of the generated products. The behavior of Ca and the interfering elements such as Fe, Ni, Co, Eu, Ba, and Sr is examined at each separation step. The purified ⁴¹Ca was measured by a liquid scintillation counter, and the quench curve and counting efficiency were determined by using a certified reference material of known ⁴¹Ca activity. The recoveries in this study ranged from 56 to 68%, and the minimum detectable activity was 50 mBq g^-1 with 0.5 g of concrete sample.

• Nuclear Engineering and Technology
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• 제54권8호
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• pp.3034-3042
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• 2022

The results of radioecological monitoring of the cooling pond Beloyarsk NPP (Russia) have been presented. The influence of waste technological waters of thermal and fast NPP reactors on the content of artificial radionuclides in surface waters and bottom sediments of the Beloyarsk reservoir has been studied. The long-term dynamics of the specific activity of ⁶⁰Co, ⁹⁰Sr, ¹³⁷Cs and ³H in the main components of the freshwater ecosystem at different distances from the source of radionuclide discharge has been estimated. Critical radionuclides (⁶⁰Co and ¹³⁷Cs), routes of their entry and periods of maximum discharge of radioisotopes into the cooling pond have been determined. It is shown that the technology of electricity generation at Beloyarsk NPP, based on fast reactors, has a much smaller effect on the flow of artificial radionuclides into the freshwater ecosystem of the reservoir. During the entire period of monitoring studies, the decrease in the specific activity of radionuclides from NPP origin in surface waters was 4.3-74.5 times, in bottom sediments 10-505 times. The maximum discharge of artificial radionuclides into the reservoir was noted during the period of restoration and decontamination work aimed at eliminating emergencies at the AMB thermal reactors of the first stage of the Beloyarsk NPP.

• 대한핵의학회지
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• 제21권2호
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• pp.167-174
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• 1987

Among noninvasive approaches for the evaluation of left ventricular performance, radionuclide ventriculography (RVG) has been shown to be of particular values. Phase analysis, recently introduced as more objective means for evaluating the temporal sequence of systolic ventricular wall motion than cine image of RVG comprises a pixel by pixel Fourier transformation of the time activity curve of a multiple gated acquisition equilibrium blood pool study. To examine the regional wall motion of ventricles in myocardial infarctions, we evaluated the phase image and histogram constructed for each ventricle by total phase angle range and full width of half maximum (FWHM). This study consisted of 7 normal subjects and 23 subjects with acute myocardial infarction. Contrast ventriculography and coronary angiography was performed in all partients with myocardial infarction. And we compared the result of phase analysis with cine image of RVG and examined the interrelationship between phase analysis and contrast ventriculography with coronary angiography. The results were as follows; 1) The total phase angle range and FWHM of LV phase histogram in myocardial infarction ($86^{\circ}\;and\;32^{\circ}$, repectively) were wider than those in normal control ($38^{\circ}\;and\;18^{\circ}$, respectively p<0.01). 2) RV phase angle range and FWHM in patients with right coronary artery (RCA) occlusion ($79^{\circ}\;and\;37^{\circ}$, respectively) were wider than those in normal control ($39^{\circ}\;and\;18^{\circ}$, respectively p<0.001) and the patients without RCA occlusion ($52^{\circ}\;and\;19^{\circ}$, respectively p<0.01). 3) Phase analysis was more sensitive (95%) than cine image of RVG (70%) for the detection of regional wall motion abnormality of LV.

• 자원리싸이클링
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• 제33권2호
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• pp.54-61
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• 2024

천연방사성핵종의 붕괴에 의해 생성된 Pb에 의해 오염된 철강을 재용해하면 Pb는 금속, 슬래그, 기상으로 분배된다. 본 연구에서는 Fe 중에 5 wt%의 안정한 Pb를 첨가하고 CaO-SiO₂-Al₂O₃-MgO계 슬래그와 함께 용융시켜 Pb의 금속/슬래그/가스상으로의 분배 거동을 조사하였다. 슬래그 염기도((wt%CaO)/(wt%SiO2))가 증가함에 따라 Fe 중 Pb 용해도는 약간 증가하는 경향을 나타내었으며, 슬래그 중 Pb는 감소하는 경향을 나타내었다. 따라서 염기도 증가에 따라 Pb의 슬래그/금속 사이의 분배비는 감소하는 경향을 나타내었다. 열역학적 계산 결과 슬래그 중 PbO의 활동도계수와 무관하게 Pb의 슬래그/Fe상 중 분배비는 매우 낮은 값으로 실험 결과와 유사한 수준을 나타내었다. Fe-Pb 중 Pb의 계산 증발속도가 Fe의 약 22배에 달하여 Pb의 대부분이 기상으로 증발되었다.

• 한국해양환경ㆍ에너지학회지
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• 제4권2호
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• pp.25-34
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• 2001

마산만에서 Ra 동위원소의 농도를 결정하는 요인을 살펴보기 위해 1개 고정정점에서 1999년 5월에서 8월까지 총 4회에 걸쳐 해수 중의 /sup 226/Ra과 /sup 228/Ra을 수심별로 측정하였다. /sup 226/Ra과 /sup 228/Ra의 농도는 강수량이 많은 하계 (8월 1일)에 비교적 높으나, 그 외의 조사시기에는 비교적 낮다. 마산만 표층수의 /sup 226/Ra의 시계열 변화는 염분과 높은 부의 상관관계를 보여 표층수의 /sup 226/Ra 농도는 저염분의 높은 /sup 226/Ra 내만수와 고염분의 낮은 /sup 226/Ra의 외양수의 혼합에 지배적인 것으로 사료된다. /sup 228/Ra//sup 226/Ra의 방사능비는 표층수 보다 저층수에서 낮고, 이는 저층수에 과량의 /sup 226/Ra 공급원이 존재한다는 것을 의미한다. 그러나 해수의 Ra 동위원소의 주요 공급원인 퇴적물 및 간극수는 /sup 226/Ra에 비해 상대적으로 풍부한 /sup 228/Ra을 함유하기 때문에 저층수의 낮은 /sup 228/Ra/sup 226/Ra 비는 /sup 226/Ra이 풍부한 해저지하수의 누출 가능성을 의미한다. 따라서 마산만에서 해저지하수 누출은 /sup 226/Ra의 농도분포를 결정하는 또다른 중요한 기작으로 사료되며, 이에 대한 집중적인 연구가 요망된다.

• Pediatric Gastroenterology, Hepatology & Nutrition
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• 제11권1호
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• pp.12-20
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• 2008

목 적: 영유아에서 위식도 역류는 흔한 질환이며, 위식도 역류의 합병증으로 위 내용물의 폐 흡인에 의한 만성 호흡기 질환이 생길 수 있으나 이를 진단하기 위한 표준적인 검사 방법이 없다. 본 연구에서는 위식도 역류와 폐 흡인 진단 방법으로서 위식도 역류 신티그래피의 유용성을 평가하고자 하였다. 방 법: 위식도 역류로 인한 흡인 폐렴이 의심된 35명의 환아와 정상 대조군 5명을 대상으로 하였다. 모든 대상아에게 $^{99m}Tc$-tin colloid를 첨가한 우유를 수유한 후 위식도 역류 신티그래피를 시행하였다. 위식도 역류를 진단하기 위해 1시간 동안 동적 영상을 촬영하였고, 폐 흡인을 진단하기 위해 6시간과 24시간 후 지연 영상으로 정적 영상을 얻었다. 폐 흡인의 진단을 위해 육안분석과 함께 양쪽 폐에 관심 영역을 설정하여 정량 분석을 시행하였다. 흡인 지수는 관심 영역에서 배경 영역의 계수치를 뺀 값으로 정의하였다. 결 과: 35명의 환아 중 23명에서 신티그래피상 위식도 역류가 관찰되었고, 정상 대조군 5명에서는 위식도 역류가 발견되지 않았다. 환아군 35명 중 24명에게 24시간 하부 식도 pH 검사를 시행하였고, 7명에서 산성역류가 확인되었다. 신티그래피와 하부 식도 pH 검사를 동시에 받은 24명 중 8명에서 두 검사의 결과가 일치하여 두 검사는 위식도 역류의 진단에 있어 일치하지 않았다. 환아군 35명 중 16명에게 흉부 전산화 단층 촬영을 시행하여 13명의 환아에서 의존성 위치에 폐 경화가 발견되어 흡인 폐렴으로 진단하였고, 이 환아들이 신티그래피에서도 폐 흡인이 있었는지 그 일치도를 알아보았을 때, 두 검사는 폐 흡인의 진단에 있어 일치하지 않았다. 한 명의 환아에서 6시간 후 지연 영상에 우폐로 역류된 방사능이 육안적으로 관찰되었다. 대조군과 비교하였을 때, 30명(85.7%)의 환아에서 흡인 지수가 결정점인 0.3보다 높아 폐 흡인의 가능성이 높은 것으로 진단하였다. 역류군과 비 역류군을 비교하였을 때, 6시간 후 지연 영상에서 흡인 지수는 역류군에서 유의하게 높았다(p<0.05). 결 론: 위식도 역류 신티그래피는 비 침습적이고 안전한 검사로 위식도 역류의 진단에 있어서는 24시간 하부 식도 pH 검사에 비하여 부족하지만 역류로 인한 소량의 폐 흡인을 진단하는데 유용하며, 앞으로 통계학적으로 의미 있는 수의 대조군 연구가 수행된다면 폐 흡인을 확진할 수 있는 진단 기준이 나올 것으로 생각된다.