• 대한핵의학회지
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• 제32권4호
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• pp.382-390
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• 1998

목적 : 이 연구의 목적은 SPECT 영상의 감쇠와 산란 현상을 보정하고 실제 임상 환경에서 상용하는 영상과 비교하여 그 효과를 평가하는 것이다. 그리고, 정확도가 개선된 영상에서 방사능양을 도출하여 SPECT 영상의 절대적인 정량화를 검증하는 것이다. 대상 및 방법: 직경이 20.0 cm인 원통형 팬톰에 삽입물로써 체적 25 ml의 폴리에틸렌 병을 6개 배치하고 배후와 다양한 비율을 이루도록 Tc-99m을 주입하였다. SPECT 기기로는 Trionix Triad xlt 20을 사용하였고 광피크 윈도 $126{\sim}154keV$, 산란 윈도 $101{\sim}123keV$에서 데이터를 얻었다. 이중에너지윈도(DEW) 방법과 Chang 방법을 사용하여 산란 및 감쇠 효과를 보정한 영상(SC+AC), 임상적으로 통용되고 있는 Chang 방법만을 사용하여 감쇠 효과를 보정한 영상(AC), 보정을 거치지 않은 영상(NONE)을 얻었다. SPECT 영상을 정량적으로 분석하기 위해 삽입물 대 배후의 방사능비(T/B), 영상대비, 절대방사능을 구하여 참값과 비교하였다. 결과: 관심영역 분석을 통한 T/B는 참값에 대하여 SC+AC 영상은 $1{\sim}20%$의 차이를 보였고 AC의 $24{\sim}37%$와 NONE의 $12{\sim}32%$에 비하여 개선되었다. 또한 SC+AC에서 영상 대비는 참값 1에 대하여 0.92로써 AC의 0.77, NONE의 0,80에 비하여 향상되었다. SPECT 영상에서 얻은 절대방사능 값은 SC+AC 영상이 참값에 대하여 $1{\sim}11%$의 오차를 나타냈으나, AC의 $22{\sim}47%$, NONE의 $2{\sim}16%$에 비하여 정확하였다. 그리고 대상물이 10.0 cm의 심부에 있을 때 절대방사능 값은 SC+AC에서 24%의 감소, AC에서 10%의 증가, NONE에서 40%의 감소를 보였다. 결론: 이 연구에서 사용한 DEW와 Chang방법에 의한 산란 및 감쇠 보정은 임상에 쉽게 적용할 수 있으며, 삽입물 대 배후의 방사능비와 영상 대비를 개선하였고 절대방사능을 정확하게 산출할 수 있었다.

• 핵의학기술
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• 제25권2호
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• pp.41-47
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• 2021

최근 사이클로트론 시설의 GMP 인증 및 핵의학과 검사 보험 미적용 등으로 인해 핵의학 검사 수가 감소함에 따라 사이클로트론도 조기에 해체될 가능성이 높다. 이에 본 연구에서는 사이클로트론 해체 시 방사성폐기물 발생량과 관련성이 높은 사이클로트론 차폐벽 내 방사성핵종을 확인하였다. 국내에는 해체가 진행중인 사이클로트론이 없으므로 사이클로트론 차폐벽 Coring이 불가능하고, 국내 모든 사이클로트론에 대한 실험을 수행하는 것은 현실적으로 불가능하다. 따라서, 대구 K대학교 병원 내 KIRAMS-13이 설치된 사이클로트론실에서 Target 진행 방향을 중심으로 총 30 곳에서 방사성핵종을 분석하였다. 본 연구에서 활용한 장비는 Thermo사의 RIIDEye이며, 측정 지점별 측정시간은 24시간으로 설정하였다. 측정 결과 일부 측정 지점에서 장반감기 방사성핵종인 Co-60과 Cs-137이 검출되었다. 또한, 가장 많은 측정 지점에서 검출된 Co-60의 방출에너지별 방사능을 확인한 결과, target 방향을 중심으로 우측 상부에서 좌측 하부로 이어지는 대각선 방향으로 방사능이 높은 것을 확인하였다. 따라서, 향후 사이클로트론 해체 전 차폐벽 coring 위치 선정 시 휴대용핵종분석기를 활용할 수 있을 것으로 예상된다. 하지만, 본 연구는 하나의 사이클로트론에 대한 실험 결과이므로 다수의 사이클로트론에 대한 추가 연구가 필요할 것으로 예상된다. 또한, 본 연구 결과는 휴대용핵종분석기를 사용한 연구결과로서 HPGe를 활용한 추가 연구를 수행하여 일치성을 확인하는 추가 연구가 필요할 것으로 판단된다. 최종적으로 다년간의 각 기관별 콘크리트 표면에서의 방사화 자료가 구축된다면, 사이클로트론 해체 준비 시 보다 정확한 방사성폐기물량을 예측할 수 있을 것으로 판단된다.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 Proceedings of the 4th Korea-China Joint Workshop on Nuclear Waste Management
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• pp.130-139
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• 2004

The cladding materials remaining after reprocessing process of the nuclear fuel, generally called as hulls, are classified as a high-level radioactive waste. They are usually packaged in the container for disposal after being compacted, melted, or solidified into the matrix. The efforts to fabricate a better ingot for a more favorable disposal to the environment have failed due to the technical difficulties encountered in the chemical decontamination method. In the early 1990s, the accumulation of radio-chemical data on hulls and the advent of new technology such as a laser or plasma have made the pre-treatment of the hulls more efficient. This paper summarizes the information regarding the radio-chemical analysis of the hull through a literature survey and determines the characteristics of the hull and depth profile of the radio-nuclides within the hull thickness. The feasibility study was carried out to evaluate the reduction of the radioactivity by peeling off the surface of the hull with the application of laser technology.

• 한국지반공학회:학술대회논문집
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• 한국지반공학회 2005년도 춘계 학술발표회 논문집
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• pp.1205-1210
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• 2005

The behavior of rock mass and solute(e.g. groundwater, radioactivity) flow in fractured rock can be directly influenced by joint roughness. The characteristics of joint roughness is also a main factor for the rock classification(e.g. RMR, Q system) which is usually used in tunnel design. Nevertheless, most of JRC estimation has been carried out only by the examination with the naked eye. This JRC estimation has a lack of objectivity because each investigator judges JRC by his subjective opinion. Therefore, it will be desirable that the assessment of JRC is performed by a numerical analysis which can give a quantitative value corresponding to the characteristics of a roughness curve. Meanwhile, roughness curves for joint surfaces which are observed in drill cores have been obtained only along linear profiles. Although roughness curves are measured in the same joint surface, they can frequently show diverse aspects in a standpoint of roughness characteristics. If roughness curves can be measured along the elliptical circumferences of joint surfaces from core scanning images or Televiewer images, they will certainly be more comprehensive than those measured along linear profiles for roughness characteristics of joint surfaces. This study is focus on dealing with (1) extracting automatically roughness curves from core scan image or Televiewer image, (2) improving the accuracy of quantitative assessment of JRC using fractal dimension concept.

• Journal of Radiation Protection and Research
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• 제9권2호
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• pp.112-117
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• 1984

A lot of radioisotopes are applied to medical fields. It's very important to measure the activities on airborne radioiodine discharged in air from $Na^{131}I$ solutions and from patients treated with radioiodine. Also surface decontamination is another one important problem to be completly solved in the isotope laboratory where there is always the possibility of radiation contamination. The Authors measured the activities on airborne radioiodine with RI collector and scintillation counter. 1. The mean accumulative activity of airborne radioiodine discharged into air from $Na^{131}I$ solution was measured as $1.3{\times}10^{-3}/hr$ rate, and the maximum value was $1.8{\times}10^{-3}/hr$. 2. Radioactivity rate per hour of airborne iodine discharged into air from patients treated with $Na^{131}I$ was measured as $6.2{\times}10^{-5}/hr$ at 8 hour after administration of radioiodine and decreased into $2{\times}10^{-6}/hr$ after 24 hour. 3. Metalic surfaces such as stainless steel or aluminum are decontaminated 5 to 6 times more rapidly than wood and concrete surfaces. 4. Decontamination with wet wiping with detergent was 9 to 10 times more rapidly than dry wiping method, but dry wiping was useful for the first step to prevent spreading and flowing from liquid radioactive materials.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2003년도 가을 학술논문집
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• pp.381-387
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• 2003

가압 경수로 사용후핵연료봉을 재처리하는 과정에서 발생되는 hull은 고준위 방사성폐기물로 분류되고 있다. 본 논문에서는 연소도 32,000MWd/tU, 냉각기간 15년(고리 1호기 cycle 4-7)인 PWR 사용후핵연료의 건식처리 공정에서 발생한 hull에 대하여 방사능적 특성 실험을 수행하였고, 문헌 조사 및 관련 코드의 계산을 통하여 가압 경수로 사용후핵연료 hull에 대한 방사화학적 특성을 조사하였다. 이를 토대로 hull에 부착되어 있는 핵물질을 레이저 또는 플라즈마 등의 건식 방법으로 제거함으로써 hull의 방사능을 저감시켜 중저준위 폐기물화하는 방안을 제시하였다.

• 방사선산업학회지
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• 제11권3호
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• pp.173-179
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• 2017

The small-scale electroplating device was designed and fabricated for Ni-63 sealed source (foil type) with a high specific activity needed for production of betavoltaic battery. The condition of Ni electroplating was optimized by using fabricated electroplating device to establish a Ni-63 electroplating condition on the Ni foil. The results showed that the optimum surface morphology and thickness of Ni deposit was obtained for 1,758 seconds at a current density of $15mA{\cdot}cm^{-2}$ with 0.5% tween 20. Radioisotope Ni-63 electroplating was implemented under established condition. The radioactivity of Ni-63 sealed source was calculated to $28mCi{\cdot}cm^{-2}$, and the thickness of Ni-63 deposit was about $2.4{\mu}m$.

• Nuclear Engineering and Technology
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• 제53권1호
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• pp.244-252
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• 2021

Wind plays an important role in cases of unexpected radioactive pollutant dispersion, deciding distribution and concentration of the leaked substance. The accurate prediction of wind has been challenging in numerical weather prediction models, especially near the surface because of the complex interaction between turbulent flow and topographic effect. In this study, we investigated the characteristics of atmospheric dispersion of radioactive material (i.e. ¹³⁷Cs) according to the simulated boundary layer around the HANARO research nuclear reactor in Korea using the Weather Research and Forecasting (WRF)-Mesoscale Model Interface (MMIF)-California Puff (CALPUFF) model system. We examined the impacts of orographic drag on wind field, stability calculation methods, and planetary boundary layer parameterizations on the dispersion of radioactive material under a radioactive leaking scenario. We found that inclusion of the orographic drag effect in the WRF model improved the wind prediction most significantly over the complex terrain area, leading the model system to estimate the radioactive concentration near the reactor more conservatively. We also emphasized the importance of the stability calculation method and employing the skillful boundary layer parameterization to ensure more accurate low atmospheric conditions, in order to simulate more feasible spatial distribution of the radioactive dispersion in leaking scenarios.

• Nuclear Engineering and Technology
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• 제51권6호
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• pp.1626-1632
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• 2019

Monitoring of environmental radioactivity is essential for ensuring the radiological safety of residents who live near nuclear power plants. Ulsan, South Korea, is surrounded by 16 nuclear power plants, the highest density in the country. In addition, the city contains facilities for conducting radiological nondestructive testing and using radioisotopes for medical purposes. It makes the confirmation of radiological safety particularly necessary. In this study, sampling points were selected based on regional characteristics, and surface water samples were pretreated and analyzed for gross beta and gamma radiation levels. In addition, the distribution of the city's gamma dose rate was determined using a mobile monitoring system and distribution visualization program. The results showed that there is no effect on the gross beta and gamma nuclides of artificial radionuclides, and the gamma dose rate of the entire region did not exceed the environmental radiation level in South Korea overall, confirming the radiological safety of the city.

• Nuclear Engineering and Technology
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• 제50권8호
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• pp.1355-1363
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• 2018

Many radionuclides exist in normal environment and artificial radionuclides also can be detected. The radionuclides ($^{131}I$) are widely used for labeling compounds and radiation therapy. In Korea, the radionuclide ($^{131}I$) is produced at the Radioisotope Production Facility (RIPF) at the Korea Atomic Energy Research Institute in Daejeon. The residents around the RIPF assume that $^{131}I$ detected in environmental samples is produced from RIPF. To ensure the safety of the residents, the radioactive concentration of $^{131}I$ near the RIPF was investigated by monitoring environmental samples along the Gap River. The selected geographical places are near the nuclear installation, another possible location for $^{131}I$ detection, and downstream of the Gap River. The first selected places are the "front gate of KAERI", and the "Donghwa bridge". The second selected place is the sewage treatment plant. Therefore, the Wonchon bridge is selected for the upstream of the plant and the sewage treatment plant is selected for the downstream of the plant. The last selected places are the downstream where the two paths converged, which is Yongshin bridge (in front of the cogeneration plant). In these places, environmental samples, including sediment, fish, surface water, and aquatic plants, were collected. In this study, the radioactive iodine ($^{131}I$) detection along the Gap River will be investigated.