• Title/Summary/Keyword: radioisotope

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Recommended Method for Radioisotope Red-Cell Survival Studies (방사성(放射性) 동위원소(同位元素)를 이용(利用)한 적혈구수명측정법(赤血球壽命測定法)(ICSH 추천))

  • Berlin, N.I.;Dudley, R.A.;Garby, L.;Heimpel, H.;Lee, M.;Lewis, S.M.;McIntyre, P.;Mollison, P.L.;Najean, Y.;Pettit, J.
    • The Korean Journal of Nuclear Medicine
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    • v.14 no.2
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    • pp.1-9
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    • 1980
  • 혈액질환(血液疾患), 특히 용혈성빈혈(溶血性貧血)을 수반(隨伴)한 경우(境遇)에 적혈구(赤血球)의 생성(生成), 파괴과정(破壞過程)을 정확히 파악하는 것은 빈혈(貧血)의 발생기전(發生機轉) 및 병인(病因), 치료(治療), 예후(豫後) 결정(決定)에 매우 중요(重要)하다. 적혈수명측정법(赤血壽命測定法)은 최근(最近) 방사성(放射性)동위원소(同位元素)를 이용(利用)한 방법(方法)이 소개된 이래 널리 시행(施行)되어 왔다. 그러나 그 방법(方法) 및 결과(結果) 해석(解釋)에 표준화(標準化)가 되어 있지 않았던 중 1971년 ICSH (International Committee for Standardization in Hematology)에서 expert panel을 갖고 ICSH 추천 방법(方法)을 발표(發表)하였고, 본지(本誌)에서도 그 내용(內容)을 게재(揭載)한 바 있다. 1980년 ICSH는 전문기관 및 전문가의 협조(協調)를 얻어 다시 expert panal을 갖은 후 1971년에 추진한 적혈구수명측정법(赤血球壽命測定法)의 일부(一部)를 수정(修正)하여 ICSH의 표준방법(標準方法)으로 발표(發表)하였다. 개정(改正)된 표준방법(標準方法)과 1971년 ICSH추친 방법(方法)과의 차이(差異)는 다음과 같다. $^{51}Cr$표지방법중(標識方法中) 참고방법(參考方法)(Reference method)인 ACD법(法)에 수정(修正)을 가하여, ACD solution 구성성분(構成成分)이 차이(差異)가 있으며, 표지(標識)$^{51}Cr$의 양(量)을 체중당(體重當) $1.5{\mu}Ci$에서 $0.5{\mu}Ci$로 제한(制限)시켰다. 투여방법(投與方法)에 대한 언급 특히 투여하는 표지적혈구(標識赤血球)의 용적을 정확하게 측정 하기 위한 방법 4가지를 추가하였고, 검체준비(檢體準備) 과정중(過程中)의 pipet error를 방지(防止)하기위해 일정(一定)한 형태의 pipet을 사용(使用)하며, 1ml의 tuterculin syringe는 사용(使用)하지 않기로 하였다. 또한 결과분석시(結果分析時) 혈구용적(血球容積)의 항정성(恒定性)을 위해 Sodium pertectnetate($^{99m}Tc$)를 이용(利用)해 혈구용적(血球容積)을 반복(反復)해 측정(測定)하도록 하였으며 이때 사용(使用)하는 방사성동위원소(放射性同位元素)는 $^{32}P$ 대신 $^{99m}Tc$로 하였다. 결과해석시(結果解釋時) IgG 항체(抗體) 또는 IgM 항체(抗體)에 따른 차이점(差異點)에 대한 고려가 추가(追加)되었다. ICSH와 국제혈액학회(國際血液學會)에서 수정(修正)된 ICSH 표준방법(標準方法)에 의한 적혈수명측정법(赤血壽命測定法)을 널리 소개(紹介)하여 결과(結果)의 표준화(標準化)를 기하고자 연관잡지(聯관(關)雜誌)에 게재(揭載)할 것을 요청(要請)하였기에 전문(全文)을 본지(本誌)에 소개(紹介)하고자 한다.

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Evaluation of Therapeutic Monitoring of Prostate Cancer (PCa) using [18F]Florastamin, Diagnostic Radiopharmaceutical for PCa: Non-clinical Ex vivo Whole-body Autoradiographic Analysis

  • Min Hwan Kim;Kyongkyu Lee;Hee Seup Kil;Soon Jeong Kwon;Yong Jin Lee;Kyo Chul Lee;Dae Yoon Chi
    • Journal of Radiopharmaceuticals and Molecular Probes
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    • v.9 no.1
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    • pp.17-21
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    • 2023
  • In this study, we evaluated the targeting of prostate cancer (PCa) using [18F]Florastamin in non-clinical study, for the purpose of therapeutic monitoring of [177Lu]Ludotadipep, a therapeutic radiopharmaceutical for PCa, [18F]Florastamin/[177Lu]Ludotadipep was co-administered to a single-individual prostate tumor bearing mouse model, mimicking clinical condition. Considering the difference in half-life of the two isotopes (18F or 177Lu), image scan of whole-body autoradiography was performed at 24 or 48 h after preparation of frozen section, respectively. Then, it was confirmed whether they showed the same targeting efficiency for the area of tumor. A tumor xenograft model was prepared using PSMA-overexpressing PC3-PIP prostate cancer cells. [18F]Florastamin [111 MBq (3 mCi) in 100 µL]/177Lu]Ludotadipep [3.7 MBq (100 µCi) in 100 µL] was co-administered through the tail vein, and 2 hours after administration, the mice were frozen, and after freezing for 24 hours, whole-body cryosection was performed at 24 h after freezing. Image scanning using cryosection was performed after 24 or 48 hours after freezing, respectively. In the scan image after 24 hours, tumor uptake of [18F] Florastamin/[177Lu]Ludotadipep were simultaneously observed specific uptake in the tumor. In the scan image after 48 hours in the same section, signal of 18F was lost by decay of radioisotope, and specific uptake image for [177Lu]Ludotadipep was observed in the tumor. Uptake of [177Lu]Ludotadipep was specific to the same tumor region where [18F]Florastamin/[177Lu]Ludotadipep was uptake. These results suggested that [18F]Florastamin showed the same tumor uptake efficiency to PCa as [177Lu]Ludotadipep, and effective therapeutic monitoring is expected to be enable using [18F]Florastamin during [177Lu]Ludotadipep therapy for PCa.

Alternative Immunossays

  • Barnard, G.J.R.;Kim, J.B.;Collins, W.P.
    • Korean Journal of Animal Reproduction
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    • v.9 no.2
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    • pp.133-139
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    • 1985
  • An immunoassay may be defined as an analytical procedure involving the competitive reaction between a limiting concentration of specific antibody and two populations of antigen, one of which is labelled or immobillized. The advent of immunoassay has revolutionised our knowledge of reproductive physiology and the practice of veterinary and clinical medicine. Radioimmunoassay (RIA) was the first of these methods to be developed, which meausred the analyte with good sensitivity, accuracy and precision (1,2). The essential components of RIA are:-(i) a limited concentration of antibodies, (ii) a reference preparation, and (iii) an antigen labelled with a radioisotope (usually tritium or iodine-125). Most procedures invelove isolating the antibody-bound fraction and measuring the amount of labelled antigen. Good facilities are available for scintilltion counting, data reduction nd statistical analysis. RIA is undergoing refinement through:-(i) the introduction of new techniques to separate the antibody-bound and free fractions which minimize the misclassification of labelled antigen into these compartments, and the amount of non-specfic binding. (3), (ii) the development of non-extration for the measurement of haptens (4), (iii) the determination of a, pp.rent free (i.e. non-protein bound) analytes (5), and (iv) the use of monoclonal antibodies(6). In 1968, Miles and Hales introduced in important new type of immunoassay which they termed immunora-diometric assay (IRMA) based on t도 use of isotopically labelled specific antibodies(7) in a move from limited to excess reagent systems. The concept of two-site IRMAs (with a capture antibody on a solid-phase, and a second labelled antibody to a different antigenic determinant of the analyte) has enabled the development of more sensitive and less-time consuming methods for the measurement of protein hormones ovar wide concentration of analyte (8). The increasing use of isotopic methos for diverse a, pp.ications has exposed several problems. For example, the radioactive half-life and radiolysis of the labelled reagent limits assay sensitivity and imposes a time limit on the usefulness of a kit. In addition, the potential health hazards associated with the use and disposal of radioactive cmpounds and the solvents and photofluors necessary for liquid scientillation counting are incompatable with the development of extra-laboratory tests. To date, the most practical alternative labels to radioisotopes, for the measurement of analytes in a concentration > 1 ng/ml, are erythrocytes, polystyrene particiles, gold sols, dyes and enzymes or cofactors with a visual or colorimetric end-point(9). Increased sensitivity to<1 pg/ml may be obtained with fluorescent and chemiluminescent labels, or enzymes with a fluorometric, chemiluminometric or bioluminometric end-point. The sensitivity of any immunoassay or immunometric assay depends on the affinity of the antibody-antigen reaction, the specific activity of the label, the precision with which the reagents are manipulated and the nonspecific background signal (10). The sensitivity of a limited reagent system for the measurement of haptens or proteins is mainly dependent upon the affinity of the antibodies and the smalleest amount of reagent that may be manipulated. Consequently, it is difficult in practice to improve on the sensitivity obtained with iodine-125 as the label. Conversely, with excess reagent systems for the measurement of proteins it is theoretically possible to increase assay sensitivity at least 1000 fold with alternative luminescent labels. To date, a 10-fold improvement has been achieved, and attempts are being made to reduce the influence of other variables on the specific signal from the immunoreaction.

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Application of peak based-Bayesian statistical method for isotope identification and categorization of depleted, natural and low enriched uranium measured by LaBr3:Ce scintillation detector

  • Haluk Yucel;Selin Saatci Tuzuner;Charles Massey
    • Nuclear Engineering and Technology
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    • v.55 no.10
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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.

Non-clinical Trials using 14C-Acetaminophen to Validate Biomedical Accelerator Mass Spectrometry System (14C-아세트아미노펜 비임상시험을 통한 생체시료 분석용 가속질량분석기의 검증)

  • Jinho Song;Jae Hoon Shim;Jung Bae Park;Chang Su Yeo;Soo Hyeon Bae;Min Sun Choi;Mi Hye Kwon;Kyeong Min Kim
    • Journal of Radiation Industry
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    • v.17 no.2
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    • pp.127-134
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    • 2023
  • Pharmacokinetic (PK) data provide pivotal information in drug development, and they are usually first studied in the preclinical stage using various animals. However, quite often, animal PK data may not match with human PK, especially in metabolites. Thus, most regulatory agencies in the world make it mandatory to obtain metabolite information using 14C radiolabeled drug in human for small molecule drug candidates. However, such studies are expensive and time consuming and they are usually done at the end of Phase II trials using ~3.7 MBq of 14C labeled drug in a limited number of human subjects. Introduction of accelerator mass spectrometry (AMS) in this kind of study has revolutionized it. Since AMS can measure 14C level as close as natural abundance, it can quantify the amounts of 14C labeled drugs and their metabolites produced in human body that consumes less than the amount of 0.0037 MBq of 14C labeled drug, a very safe level of radioactive dose in human. Therefore, it is now possible to conduct human 14C studies safely in early clinical trials without spending hefty amount of money and time. Korea Radioisotope Center for Pharmaceuticals(KRICP) at Korea Institute of Biological and Medical Sciences(KIRAMS) has established an AMS facility in 2018, housing a 0.5MV AMS manufactured at the US National Electrostatics Corps (NEC). The AMS instrument has been validated using various standard samples that have been prepared at Lawrence Livermore National Laboratory in the US, a worldly reputable provider of AMS standards. In this paper, we present a mass balance study for acetaminophen in rats using AMS and prove that the study results are equivalent with those of literature, which shows the AMS facilities at KRICP has successfully installed and be ready to be used in the various PK studies using 14C labelled compounds for new drug development.

Multivariate statistical study on naturally occurring radioactive materials and radiation hazards in lakes around a Chinese petroleum industrial area

  • Yan Shi;Junfeng Zhao;Baiyao Ding;Yue Zhang;Zhigang Li;Mohsen M.M.Ali;Tuya Siqin;Hongtao Zhao;Yongjun Liu;Weiguo Jiang;Peng Wu
    • Nuclear Engineering and Technology
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    • v.56 no.6
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    • pp.2182-2189
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    • 2024
  • The high-purity germanium gamma-ray spectrometer was used to measure the radioisotope in surface water of lakes in a Chinee petroleum industrial area. 92 samples were collected from surface water of three lakes. Activity concentrations of 232Th, 226Ra and 40K in three lakes were measured, distributed in the range of 101.8-209.4, 192.1-224.9 and 335.0-548.9 mBq/L, respectively. Results were all within the limits of WHO and China. Potential environmental and health risks were assessed by calculating some radiation hazard indicators, radium equivalent index, annual effective dose, excess lifetime cancer risk, absorbed dose rate, external hazard index, internal hazard index, annual gonadal dose equivalent, activity utilization index and representative gamma index, which ranged 0.38-0.54 Bq/L, 0.06-0.08 mSv/y, 0.23 × 10-3-0.31 × 10-3, 0.17-0.24 nGy/h, 1.01 × 10-3-1.46 × 10-3, 1.55 × 10-3-2.02 × 10-3, 1.16-1.66 μSv/y, 3.13 × 10-3-4.45 × 10-3 and 2.60 × 10-3-3.77 × 10-3. The results were all at acceptable levels, meaning no impact on human health. The relationship between the electrical conductivity of surface water and the activity concentration of 232Th, 226Ra and 40K was evaluated. The electrical conductivity value was 0.241-0.369 mS/cm, showing a significant correlation coefficient between 226Ra and 40K and electrical conductivity. Multivariate statistical methods were used to determine the relationship between the activity concentrations of 232Th, 226Ra, and 40K, radiation hazard indicators and electrical conductivity.

Studies on the Use of Radioisotope Tracer Techniques to Investigate and Improve the Root Activities in Rice Plant(I) - Effect of Water Control in Soil of the Paddy Field Lacking in the Special Mineral Nutritions - (방사성(放射性) 동위체도입(同位體導入)과 그 추적기술(追跡技術)에 의(依)한 수도근계(水稻根系) 활성상(活性相)의 해명(解明)과 개선(改善)에 관(關)한 연구(硏究) - 특수성분(特殊成分) 결핍(缺乏) 답토양(沓土壤)에서의 용수조절(用水調節) 효과(效果)에 대(對)하여-(제1보)(第1報) -)

  • Ahn, Hak-Soo;Chung, Hee-Don;Kim, Kyu-Won;Shim, Sang-Chil
    • Applied Biological Chemistry
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    • v.15 no.1
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    • pp.77-84
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    • 1972
  • A field experiment was conducted to determine the factors responsible in limiting nutrient up take and root activity in low productive paddy fold. Radiosotope of phosphorus-32 was used as a tracer. Results of the study were as follows: 1. On yield components responsible for increase yield indicated that number of ears per panicle and ripening ratio were closely related to increase yield. 2. Root volume or root feeding area has significant influence in increasing rice yield. 3. Root volume indicative of root activity and nutrient uptake can be effected by reasonable water control. 4. The combined application of calcium, silica, and magnesium(as a fused magnesium phosphate. the Kyun-gi Chemical Co. products.) with water control, although under conditions of large amount application of nitrogen, was found to be increased the maturing rate. 5. In the plots of water control, the number of roots per one volume were less than that of the continuous flooding plots, but the weight per root was heavier than the flooding plot ones. 6. Improvement of the present native culture method could effectively increase paddy rice yield.

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Studies on the Use of Radioisotope Tracer Technique to Investigate and Improve the Root Activities in Rice Plant (II) - Effect of Application of Several Kinds of Phosphorous Fertilizer - (방사성동위체(放射性同位體) 도입(導入)과 그 추적기술(追跡技術)에 의(依)한 수도근계(水稻根系) 활성상(活性相)의 해명(解明)과 개선(改善)에 관(關)한 연구(硏究) - 인산질(燐酸質) 비료(肥料)의 비종별(肥種別) 시용효과(施用效果)에 대(對)하여 - (제2보)(第2報))

  • Ahn, Hak-Soo;Chung, Hee-Don;Ahn, Jon-Sung;Ro, Jun-Chong;Kim, Kyu-Won;Shim, Sang-Chil
    • Applied Biological Chemistry
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    • v.15 no.1
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    • pp.85-92
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    • 1972
  • The field experiment was performed to investigate the effects of various kinds of phosphorus fertilizers such as double superphosphate, fused magnesium phosphate and Simagcarin (both the Kyun-gi Chemical Co, products) on the physiological roles in development of root system, growth and yield compositions of rice plant. Radioactive phosphoric acid $(H_3\;^{32}PO_4)$ was applied to measure the root activity. 1. The number of total tillers was significantly increased in double superphosphate plots, but the rate of fruitful tillers was more numerous in the fused magnesium phosphate and the Simagcarin plots than that of the other plots. 2. The grain yield was much more obtained in the fused magnesium phosphate and Simagcarin plots (no significant difference were found between both of plots) than the double superphosphate and control plots. It seemed due to the increasing of seedbearing rate and number of fruitful tillers. 3. In double superphosphate plots, root system was mostly developed near topsoil areas, but fused magnesium phosphate and the Simagcarin plots, root system was uniformly distributed from topsoil to subsoil areas. 4. As the results of those experiments, fused magnesium phosphate and Simagcarin was demonstrated to be soil amendmentical materials rather than the phosphorus fertilizers, especially in low productive paddy soils which lack the special mineral nutritions.

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Study for Automatic Exposure Control Technique (AEC) in SPECT/CT for Reducing Exposure Dose and Influencing Image Quality (SPECT/CT에서 자동노출제어(AEC)를 이용함으로써 얻어지는 영상의 질 평가와 피폭선량 감소에 관한 고찰)

  • Yoon, Seok-Hwan;Lee, Sung-Hwan;Cho, Seong-Wook;Kim, Jin-Eui
    • The Korean Journal of Nuclear Medicine Technology
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    • v.18 no.2
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    • pp.33-38
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    • 2014
  • Purpose Auto exposure control (AEC) in SPECT/CT automatically controls the exposure dose (mA) according to patient's shape and size. The aim of this study was to evaluate the effect of AEC in SPECT/CT on exposure dose reduction and image quality. Materials and Methods The model of SPECT/CT used in this study was Discovery 670 (GE, USA), Smart mA for AEC; and $^{99m}Tc$ as a radioisotope. To compare SPECT and CT images by CT exposure dose variation, we used a standard technique set at 80, 100, 120, 140 kVp, 10, 30, 50, 100, 150, 200, 250 mA, and AEC at 80, 100, 120, 140 kVp, 10-250 mA. To evaluate resolution and contrast of SPECT images, triple line phantom and flangeless Esser PET phantom were used. For CT images, noise and uniformity were checked by anthropomrphic chest phantom. For dose evaluation to find DLP value, anthropomorphic chest phantom was used and the CT protocol of torso was applied by standard technique (120 kVp, 100 mA) and AEC (120 kVp, 10-250 mA). Results When standard and AEC were applied, the resolutions at SPECT images with attenuation correction (AC) were the same as FWHM by center 3.65 mm, left 3.48 mm, right 3.61 mm. Contrasts of standard and AEC showed no significant difference: standard 53.5, 29.8, 22.5, 15.8, 6.0, AEC 53.5, 29.6, 22.4, 15.7, 6.1 In CT images, noise values at standard and AEC were 15.4 and 18.5 respectively. The application of AEC increases noise but the value of coefficient variation were 33.8, 24.9 respectively, obtaining uniform noise image. The values of DLP at standard and AEC were 426.78 and 352.09 each, which shows that the application of AEC decreases exposure dose more than standard by approximately 18%. Conclusion The results of our study show that there was no difference of AC in SPECT images based on the CT exposure dose variation at SPECT/CT images. It was found that the increased CT exposure dose leads to the improvement of CT image quality but also increases the exposure dose. Thus, the use of AEC in SPECT/CT contributes to obtaining equal AC SPECT images, and uniform noise in CT images while reducing exposure dose.

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Consideration of Radioactive Contamination Materials Disposal (방사성오염물질 처분에 대한 고찰)

  • Im, Hyun-Jin;Kim, Tae-Yeob;Lee, Hong-Jae;Kim, Jin-Eui;Kim, Hyun-Joo
    • The Korean Journal of Nuclear Medicine Technology
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    • v.14 no.2
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    • pp.128-132
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    • 2010
  • Purpose: Nuclear medicine general operation room is radioactive control room which is used for the handling of radioisotope(R.I). Radioactive contamination materials must be under control and separated from general trash. With this experiments, we want to actively suggest the guideline of controling and operating radioactive contamination materials by measuring contamination degree and analyzing the causes which is not realized so far. Materials and Methods: Materials are selected from Oct. 2009 to March. 2010. salines which are used for labelling radiophamaceuticals and generator cap, saline needle cap, $^{99m}Tc$-needle cap saline vial which is generated from $^{99}Mo$/$^{99m}Tc$ generator. After measuring each surface contamination degree by survey meter, mean value and standard deviation one were solved out. Results: In result, After measuring surface contamination degree, radioactivity of saline for labelling radiophamaceuticals showed $14429{\pm}26378$ cpm (p<0.05) and in measured generators, foreign imported things showed that generator cap : $9{\pm}21$ cpm, saline vial : $17{\pm}28$ cpm. saline needle cap : $35{\pm}66$ cpm, $^{99m}Tc$-needle cap : $9{\pm}21$ cpm, saline vial $13{\pm}28$ cpm. domestic things showed that generator cap : $22852{\pm}52545$ cpm, saline needle cap : $87367{\pm}109711$ cpm, $^{99m}Tc$-needle cap : $9008{\pm}10459$ cpm, saline vial : $186416{\pm}158196$ cpm (p<0.05). Conclusion: The saline which is used for labelling, exceeded 1/10 of maximum permissible range. this is generated from radiophamaceuticals dilution procedure. and In generators, radioactive value of foreign import things showed closely background value. but which of domestic thing showed that exceeded more than 1000 values 1/10 of maximum permissible range. the causes of that is domestic generator is contaminated in manufacturing procedure. So, to dispose radioactive contamination materials which is could betaken out of, the control and operation must be radical under controlled by radioactive measuring, recording and equipping of its own. if this is kept well, we can prevent surely that radioactive waste could be disposed like as general trash.

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