• Journal of Radiation Protection and Research
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• 제28권2호
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• pp.117-125
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• 2003

$^{99m}Tc$ 표지 방사성의약품을 이용한 핵의학 영상검사를 받은 환자들에서 방사선 적응반응이 개인간에 어느 정도 차이가 있는지 알아보고자 하였다. $^{99m}Tc-DTPA$ 신장 신티그라피를 시행한 환자 23명, $^{99m}Tc-MDP$ 골 신티그라피를 시행한 환자 18명 및 $^{99}mTc-TF$ 심근관류 신티그라피를 시행한 환자 21명, 총 62명의 환자를 대상으로 방사성의약품 주사 전, 그리고 주사후 4시간째 채혈하여 림프구를 채취 배양하였다. 고선량 방사선조사는 배양 46시간째 $^{137}Cs$ 조사기를 사용하여 2 Gy의 감마선을 조사하였다. 불안정 염색체의 발생빈도를 Ydr값으로 표현하였고, 방사선 적응반응 지수(k)는 저선량 전처치후 Ydr값을 전처치 전 Ydr값으로 나누어 k값이 1 미만일 때 방사선 적응반음이 유도되는 것으로 간주하였다. 대상환자 62명 중 61명에서 방사선 적응반응이 유도되었고 $^{99m}Tc-DTPA,\;^{99m}Tc-MDP$ 및 Tc-99m-TF 환자군에서 k값의 변동계수 (CV)는 각각 35%, 34%, 21%였다. k값은 성별, 나이 및 병명과 상관관계가 없었다. 핵의학검사를 시행한 환자들에서 방사성 의약품에 의해 유도된 방사선 적응반응은 다양한 개인차가 있었으며, 성별, 나이 또는 병명과 관계없는 다른 원인에 의한 것으로 판단되었다.

• 대한의용생체공학회:의공학회지
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• 제18권3호
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• pp.291-299
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• 1997

As a microimaging device detecting gamma rays emitted from small lesions or tumors during operation, the intraoperative surgical probe has been proposed and is now under development. We have designed a multipurpose portable gamma prove system and evaluated the performance both for the absolute counting purpose of residual radioactivities and for the localizing capability of gamma events using the NaI(Tl) crystal and two types of photomultiplier tubes(PMTs). Counting efficiencies in the range of routine clinical use of radiation dose were measured using the assembly of single channel PMTs and 0.5 inch thick NaI(Tl) crystal of 1 inch diameter. The positioning of gamma events for imaging purpose requires the multiple channel PMTs with appropriate positioning electronics. We have designed a simple and reliable positioning circuit based on the concept of modified Anger. In preliminary experiments using the multiple channel PMT of 3 inch diameter and the dim lighth source, we were able to trace and localize the correct position with reduced positioning error by the use of two multiplier/divider chipset and simplified peripherals. The energy resolutions for the counting gamma probe measured as full width at half maximum(FWHM) for Cs-137, F-18, Tc-99m were 12%, 13%, and 36%, respectively. The spatial resolution for the imaging gamma probe measured as FWHM for green LED was 2.9 mm. The results indicate that the currently developing probe is very promising and could be very useful for many applications in nuclear medicine. Future studies will include developing collimators, improving interface hardwares, and evaluating the system with clinical data.

• 방사성폐기물학회지
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• 제9권2호
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• pp.81-86
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• 2011

폴리머 시멘트 고화체는 일반 몰타르 내의 시멘트 수화물을 폴리머 개질제를 이용하여 부분적으로 대체함으로써 그 기능을 강화시킨 복합재료로써, 특히 시멘트 몰타르에 폴리머를 첨가하는 것은 그 화학적 내구성을 향상시킨다고 알려져 있다 따라서 본 연구에서는 고화재료로서의 폴리머 시멘트에 대한 낮은 침투성 및 낮은 이온 확산도 등과 같은 향상된 화학적 내구성을 확인하기 위하여 폴리머 시멘트 시편들을 제조하였다. 이때 폴리머의 함량은 0 에서부터 30%까지 변화시켰으며, 물에 대한 시멘트 비 (W/C)를 33%와 50%로 각각 유지 시켰다. 충분히 경화시킨 후에, 제조된 시편들에 대한 구조적 건전성을 압축강도와 수침법에 의한 공극도를 통하여 평가하였다. 그 결과, W/C 비가 33%이고, 폴리머 함량이 약 10%인 폴리머 시멘트 시편에서 가장 향상된 개질변화를 얻을 수 있었다. 끝으로 이 최적의 조합비를 가지는 시편에 대하여 ANS 16.1에 따르는 침출시험을 수행하였으며, 그 결과를 일반 시멘트 고화체와 비교하였다.

• 대한방사선기술학회지:방사선기술과학
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• 제40권4호
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• pp.605-611
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• 2017

검출기의 구조를 PENELOPE의 코드를 사용하여 전산모사 하였다. 표준혼합시료(450, 1,000 ml)를 사용하여 다양한 밀도와 높이에 따른 저에너지(59.54 keV)부터 고 에너지(1,836.05)에 대한 측정효율과 PENELOPE 전산모사에서 구한 효율을 비교하였으며, 또한 자체흡수에 대한 효율을 보정하여 다양한 환경시료에 적용하여 검출하한치를 알아보고자 한다. 표준혼합선원의 전체에너지 피크효율 값을 적용하여 높이에 따른 효율변화를 측정치와 PENELOPE의 전산모사 값과 비교하였다. 여기서 구한 값들을 자체흡수 보정하여 구한 효율을 실제 환경시료에 적용하여 검출하한치 값들을 구하였다. 밀도보정인자는 밀도가 $0.4g/cm^3$에서 241Am(59.54 keV)의 밀도보정인자는 1.15, PENELOPE 전산모사에서는 1.153, 137CS(661.66 keV) 에서는 $1.06g/cm^3$, PENELOPE 전산모사에서는 1.064, 88Y(1,836.04 keV)에 대한 밀도보정인자는 1.03, PENELOPE 전산모사에서는 1.033으로 불확도는 1% 이내에서 잘 일치함을 확인하였다. 환경 시료의 밀도에 따른 방사능 농도는 시료량이 많을수록, 측정시간이 증가할수록 MDA(Minimum Detectable Activity) 값이 감소함을 확인할 수 있었다.

• 방사선산업학회지
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• 제5권4호
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• pp.337-345
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• 2011

In order to provide an effective preparedness for a nuclear or radiological emergency happening in the domestic or neighborhood countries and to solve the vague fear of the people for the ingestion of radioactive livestock products, the establishment of national guideline level for radionuclides in feed is urgently necessary. This is because it is important to secure the safety and to manage the crisis in the agricultural, fishery and food sector by performing the effective safety control during and after nuclear incident. This study was performed to investigate the report cases of international organizations and foreign countries to set up a domestic control standard for managing radioactive substances that may be contaminated in animal feeds due to the nuclear power plant incident. In addition, an attempt was made to provide a useful reference that can help prepare a domestic control standard, using a coefficient that can consider the transfer into livestock through the intake of radioactive contaminated animal feeds. The standard radioisotopes investigated were confined to radioactive cesium ($^{137+134}Cs$) and iodine ($^{131}I$). Guideline level for the radionuclides was calculated by using the transfer coefficient factor and the maximum daily intake of animal feed provided by IAEA. For example, the maximum daily intake of animal feed was set as $25kg\;d^{-1}$ for dairy cows, $10kg\;d^{-1}$ for beef cattle, $3.0kg\;d^{-1}$ for pigs and $0.15kg\;d^{-1}$ for chickens. The result values for radioactive cesium were calculated as $8,696Bq\;kg^{-1}$, $4,545Bq\;kg^{-1}$, $1,667Bq\;kg^{-1}$ and $2,469Bq\;kg^{-1}$, respectively. The results for radioactive iodine showed the ranges between $741Bq\;kg^{-1}$ and $76,628Bq\;kg^{-1}$. These data can be utilized as a scientific reference for the preparation of a crisis management manual for the emergency control due to nuclear power plant accident in Korea and neighboring country. These results will contribute to establish the safe feed management system at national level as manual for responding the radioactive exposure of agricultural products and animal feeds, which are currently not established.

• Journal of Radiation Protection and Research
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• 제44권2호
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• pp.64-71
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• 2019

Background: It is very difficult to distinguish between a radioactive contamination source and background radiation from natural radionuclides in the marine environment by means of online monitoring system. The objective of this study was to investigate a statistical process for triggering abnormal level of count rate data measured from our on-line seawater radioactivity monitoring. Materials and Methods: Count rate data sets in time series were collected from 9 monitoring posts. All of the count rate data were measured every 15 minutes from the region of interest (ROI) for $^{137}Cs$ ($E_{\gamma}=661.6keV$) on the gamma-ray energy spectrum. The Shewhart ($3{\sigma}$), CUSUM, and Bayesian S-R control chart methods were evaluated and the comparative analysis of determination methods for count rate data was carried out in terms of the false positive incidence rate. All statistical algorithms were developed using R Programming by the authors. Results and Discussion: The $3{\sigma}$, CUSUM, and S-R analyses resulted in the average false positive incidence rate of $0.164{\pm}0.047%$, $0.064{\pm}0.0367%$, and $0.030{\pm}0.018%$, respectively. The S-R method has a lower value than that of the $3{\sigma}$ and CUSUM method, because the Bayesian S-R method use the information to evaluate a posterior distribution, even though the CUSUM control chart accumulate information from recent data points. As the result of comparison between net count rate and gross count rate measured in time series all the year at a monitoring post using the $3{\sigma}$ control charts, the two methods resulted in the false positive incidence rate of 0.142% and 0.219%, respectively. Conclusion: Bayesian S-R and CUSUM control charts are better suited for on-line seawater radioactivity monitoring with an count rate data in time series than $3{\sigma}$ control chart. However, it requires a continuous increasing trend to differentiate between a false positive and actual radioactive contamination. For the determination of count rate, the net count method is better than the gross count method because of relatively a small variation in the data points.

• 한국방사선학회논문지
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• 제14권7호
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• pp.849-856
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• 2020

감마선 에너지 스펙트럼 연구에서 에너지 분석을 통한 핵종 분석은 매우 중요하다. 감마선 에너지 측정에 일반적으로 사용되는 고순도 Ge 검출기는 높은 에너지 분해능과 상대적으로 높은 검출 효율 때문에 일반적으로 사용된다. 그러나 반도체 검출기는 높은 에너지 분해능을 유지하기 위해 주변 환경에서 발생하는 노이즈를 효과적으로 차단하지 않으면 원래의 성능을 유지하기 어렵고 고가의 장치의 효과를 얻지 못하는 문제점이 있. 따라서 본 연구에서는 검출기에서 발생하는 전기적 노이즈를 제거하기 위해 접지 루프 아이솔레이터 (NEXT-001HDGL)를 사용했다. 에너지 분해능 향상 효과를 테스트하기 위해 양성자 가속기 KOMAC에 새로 설치된 HPGe 검출 장치를 사용했다. 감마선 에너지 2614 keV의 경우 에너지 분해능이 (0.16 ± 0.02) %에서 (0.11 ± 0.01) %로 개선되었고, 감마선 에너지 662 keV의 경우 에너지 분해능이 (0.72 ± 0.07) %에서 0.27 ± 0.03 %로 향상되었다. 이 결과는 KOMAC (Korea Multi-Purpose Accelerator Complex)의 HPGe 검출 장비를 이용한 감마선 스펙트럼 연구에 매우 유용한 것으로 판단된다.

• Journal of Radiation Protection and Research
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• 제47권1호
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• pp.16-21
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• 2022

Background: Epidemiological observations such as mental retardation, physical deformities, etc., in children besides different types of cancer in the adult population of the Malwa region have been reported. The present study is designed to get insight into the role of naturally occurring radioactive material (NORM) in causing detrimental health effects observed in the general population of this region. Materials and Methods: Deep soil samples were collected from different locations in the Malwa region. Their activity concentrations were determined using low-level background gammaray spectrometry. High efficiency and high purity germanium detector capped in a lead-shielded chamber having a resolution of 1.8 keV at 1,173 keV and 2.0 keV at the 1,332 keV line of ⁶⁰Co was used in the present work. Data were evaluated with Genie-2000 software. Results and Discussion: Mean activity concentrations of ²³⁸U, ²³²Th, and ⁴⁰K in deep soil were found to be 101.3 Bq/kg, 65.8 Bq/kg, and 688.6 Bq/kg, respectively. The mean activity concentration of ²³⁸U was found to be three and half times higher than the global average prescribed by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR). It was further observed that the activity concentration of ²³²Th and ⁴⁰K has a magnitude that is nearly one and half times higher than the global average prescribed by UNSCEAR. In addition, the radioisotope ¹³⁷Cs which is likely to have its origin in radiation fallout was also observed. It is postulated that the NORM present in high quantity in deep soil somehow get mobilized into the water aquifers used by the general population and thereby causing harmful health problems. Conclusion: It can be stated that the present work has been able to demonstrate the use of low background gamma-ray spectrometry to understand the role of NORM in causing health-related effects in a general population of the Malwa region of Punjab, India.

• Nuclear Engineering and Technology
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• 제55권10호
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• pp.3913-3923
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• 2023

Todays, medium energy resolution detectors are preferably used in radioisotope identification devices(RID) in nuclear and radioactive material categorization. However, there is still a need to develop or enhance « automated identifiers » for the useful RID algorithms. To decide whether any material is SNM or NORM, a key parameter is the better energy resolution of the detector. Although masking, shielding and gain shift/stabilization and other affecting parameters on site are also important for successful operations, the suitability of the RID algorithm is also a critical point to enhance the identification reliability while extracting the features from the spectral analysis. In this study, a RID algorithm based on Bayesian statistical method has been modified for medium energy resolution detectors and applied to the uranium gamma-ray spectra taken by a LaBr3:Ce detector. The present Bayesian RID algorithm covers up to 2000 keV energy range. It uses the peak centroids, the peak areas from the measured gamma-ray spectra. The extraction features are derived from the peak-based Bayesian classifiers to estimate a posterior probability for each isotope in the ANSI library. The program operations were tested under a MATLAB platform. The present peak based Bayesian RID algorithm was validated by using single isotopes(²⁴¹Am, ⁵⁷Co, ¹³⁷Cs, ⁵⁴Mn, ⁶⁰Co), and then applied to five standard nuclear materials(0.32-4.51% at.²³⁵U), as well as natural U- and Th-ores. The ID performance of the RID algorithm was quantified in terms of F-score for each isotope. The posterior probability is calculated to be 54.5-74.4% for ²³⁸U and 4.7-10.5% for ²³⁵U in EC-NRM171 uranium materials. For the case of the more complex gamma-ray spectra from CRMs, the total scoring (ST) method was preferred for its ID performance evaluation. It was shown that the present peak based Bayesian RID algorithm can be applied to identify ²³⁵U and ²³⁸U isotopes in LEU or natural U-Th samples if a medium energy resolution detector is was in the measurements.

• 한국가금학회지
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• 제38권2호
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• pp.137-144
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• 2011

본 시험은 토종닭의 교배 조합이 계육의 지방산과 아미노산 및 핵산 관련 물질 함량에 미치는 영향을 조사하기 위하여 수행되었다. 공시계는 4개 교배 조합으로 발생된 3원 교잡종을 이용하였다. 시험 설계는 A(CS${\times}$B), B(CH${\times}$S), C(RS${\times}$H), D(백세미)로 하였으며, 4처리구에 따라 암수 각각 9반복, 반복당 10수씩($4{\times}2{\times}9{\times}10$) 총 720수를 완전 임의 배치하였다. 시험 사료는 제시한 옥수수-대두박 위주의 준육용계 사료를 자체 제작하여 이용하였다. 5주령 계육의 포화지방산의 함량은 C처리구에서 가장 낮았으며, A처리구가 가장 높았다(p<0.05). 10주령 계육의 포화지방산의 함량은 5주령 계육과 마찬가지로 C처리구에서 가장 낮았으며, A처리구가 가장 높았다(p<0.05). 계육의 아미노산 함량은 모든 계육의 필수 아미노산 함량은 lysine, leucine, arginine, phenylalanine 등의 순이었고, 비필수 아미노산 함량은 glutamic acid, aspartic acid, alanine 등의 순이었다. 5주령에서는 필수 아미노산 중 valine, leucine, phenylalanine 및 lysine은 A계통에서 가장 낮게 나타났으며, phenylalanine과 lysine 함량은 B계통에서 가장 높았다(p<0.05). 비필수 아미노산 중 cystine, aspartic acid, glycine, alanine 및 proline은 A계통에서 가장 낮았고(p<0.05), 다른 계통들 사이에서는 차이가 없었다. 10주령 계육의 아미노산 함량은 모든 처리구에서 유의적인 차이가 없었다. 계육의 핵산 관련 물질 중 hypoxanthine(Hx)은 5주령에서 C처리구가 14.5%로 가장 높게 나타났으나, 10주령에서는 B처리구가 9.29%로 가장 높게 나타났다(p<0.05). 처리구간 계육의 Inosine monophosphate(IMP)는 각각 131.4 mg/100 g, 187.7 mg/100 g, 250.2 mg/100 g 및 214.0 mg/100 g으로 A, B, C처리구 사이에 유의차가 있었다(p<0.05). 10주령의 IMP는 C처리구가 258.6 mg/100 g으로 가장 높았고(p<0.05), A, B, D처리구 사이에서는 차이가 없었다. 5주령의 adenosine mono phosphate(AMP)는 처리구간 차이가 없었으나, 10주령에서는 5.46 mg/100 g, 5.96 mg/100 g, 5.45 mg/100 g 및 5.47 mg/100 g으로 B처리구에서 가장 높게 나타났다(p<0.05).