• Journal of Radiation Protection and Research
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• 제26권3호
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• pp.215-224
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• 2001

In order to comply with revised national regulationson radiological protection and to implement recent nuclear data and dose conversion factors, KOPEC developed a new point kernel gamma and beta ray shielding analysis computer program. This new code, named VisualShield, adopted mass attenuation coefficient and buildup factors from recent ANSI/ANS standards and flux-to-dose conversion factors from the International Commission on Radiological Protection (ICRP) Publication 74 for estimation of effective/equivalent dose recommended in ICRP 60. VisualShieid utilizes graphical user interfaces and 3-D visualization of the geometric configuration for preparing input data sets and analyzing results, which leads users to error free processing with visual effects. Code validation and data analysis were performed by comparing the results of various calculations to the data outputs of previous programs such as MCNP 4B, ISOSHLD-II, QAD-CGGP, etc.

• Nuclear Engineering and Technology
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• 제33권2호
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• pp.156-165
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• 2001

A radiological safety assessment was performed for a hypothetical near-surface radioactive waste repository as a simple screening calculation to identify important nuclides and to provide insights on the data needs for a successful demonstration of compliance. Individual effective doses were calculated for a conservative ground water pathway scenario considering well drilling near the site boundary. Sensitivity of resulting ingestion dose to input parameter values was also analyzed using Monte Carlo sampling. Considering peak dose rate and assessment time scale, C-14 and T-129 were identified as important nuclides and U-235 and U-238 as potentially important nuclides. For C-14, the dose was most sensitive to Darcy velocity in aquifer The distribution coefficient showed high degree of sensitivity for I-129 release.

• Pediatric Gastroenterology, Hepatology & Nutrition
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• 제19권3호
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• pp.186-192
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• 2016

Purpose: To evaluate the correlation between colon transit time (CTT) test value and initial maintenance dose of polyethylene glycol (PEG) 4000 or lactulose. Methods: Of 415 children with chronic functional constipation, 190 were enrolled based on exclusion criteria using the CTT test, defecation diary, and clinical chart. The CTT test was performed with prior disimpaction. The laxative dose for maintenance was determined on the basis of the defecation diary and clinical chart. The Shapiro-Wilk test and Pearson's and Spearman's correlations were used for statistical analysis. Results: The overall group median value and interquartile range of the CTT test was 43.8 (31.8) hours. The average PEG 4000 dose for maintenance in the overall group was $0.68{\pm}0.18g/kg/d$; according to age, the dose was $0.73{\pm}0.16g/kg/d$ (<8 years), $0.53{\pm}0.12g/kg/d$ (8 to <12 years), and $0.36{\pm}0.05g/kg/d$ (12 to 15 years). The dose of lactulose was $1.99{\pm}0.43mL/kg/d$ (<8 years) or $1.26{\pm}0.25mL/kg/d$ (8 to <12 years). There was no significant correlation between CTT test value and initial dose of laxative, irrespective of the subgroup (encopresis, abnormal CTT test subtype) for either laxative. Even in the largest group (overall, n=109, younger than 8 years and on PEG 4000), the correlation was weak (Pearson's correlation coefficient [R]=0.268, p=0.005). Within the abnormal transit group, subgroup (n=73, younger than 8 years and on PEG 4000) correlation was weak (R=0.267, p=0.022). Conclusion: CTT test value cannot predict the initial maintenance dose of PEG 4000 or lactulose with linear correlation.

• Nuclear Engineering and Technology
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• 제56권4호
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• pp.1225-1233
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• 2024

Level 3 probabilistic safety assessment (PSA) is performed to calculate radionuclide concentrations and exposure dose resulting from nuclear power plant accidents. To calculate the external exposure dose from the released radioactive materials, the radionuclide concentrations are multiplied by two factors of dose coefficient and a finite cloud dose correction factor (FCDCF), and the obtained values are summed. This indicates that a standard set of FCDCFs is required for external exposure dose calculations. To calculate a standard set of FCDCFs, the effective distance from the release point to the receptor along the wind direction should be predetermined. The TID-24190 document published in 1968 provides equations to calculate FCDCFs and the resultant standard set of FCDCFs. However, it does not provide any explanation on the effective distance required to calculate the standard set of FCDCFs. In 2021, Sandia National Laboratories (SNLs) proposed a method to predetermine finite effective distances depending on the atmospheric stability classes A to F, which results in six standard sets of FCDCFs. Meanwhile, independently of the SNLs, the authors of this paper discovered that an infinite effective distance assumption is a very reasonable approach to calculate one standard set of FCDCFs, and they implemented it into the multi-unit radiological consequence calculator (MURCC) code, which is a post-processor of the level 3 PSA codes. This paper calculates and compares short- and long-range FCDCFs calculated using the TID-24190, SNLs method, and MURCC method, and explains the strength of the MURCC method over the SNLs method. Although six standard sets of FCDCFs are required by the SNLs method, one standard sets of FCDCFs are sufficient by the MURCC method. Additionally, the use of the MURCC method and its resultant FCDCFs for level 3 PSA was strongly recommended.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2019년도 춘계학술논문요약집
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• pp.349-350
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• 2019

• 한국의학물리학회지:의학물리
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• 제11권2호
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• pp.91-99
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• 2000

본 연구는 선형 가속기에서 나오는 고 에너지 광자빔 조사를 받은 환자 내부의 선량 분포를 조사문 선량 분포로부터 재구성하는 방법을 개발하기 위한 기초 연구로서 삼차원 선량 분포를 재구성하는 방법을 제시하고 이 방법을 전산모사를 통해 평가하였다. 본 연구에서 제안하는 방법은 환자나 팬톰 내부의 임의의 지점에서 흡수된 선량과 그 지점에 대응되는 조사문 선량의 측정 지점에서 흡수된 선량의 차이를 계산하여 측정된 조사문 선량 분포로부터 환자나 팬톰 내부의 선량분포를 얻는 것이다. 선량의 차이는 역제곱법칙과 선형감쇄계수, 그리고 Monte Carlo 프로그램을 이용하여 환자나 팬톰의 CT 정보로부터 계산한 산란선량과 주선량의 비(scatter to primary dose ratio)를 이용하여 계산한다. 이 방법을 시험하기 위해 여러 종류의 균질 혹은 비균질 팬톰의 조사문 선량 분포를 Monte Carlo 전산모사로 계산한 뒤 팬톰 내부의 선량 분포를 재구성하였다. 광자빔은 1.5 MeV의 단일에너지를 사용하였고 Monte Carlo 프로그램은 EGS4를사용하였다. 본 연구의 방법을 사용하여 재구성된 팬톰 내부의 선량 분포와 Monte Carlo로 계산한 팬텀 내부의 선량 분포와 비교하였다. 비교 결과 오차 -4%∼+2% 이내로 일치하였다. 이 방법은 다른 in vivo dosimetry 방법을 대신하여 환자내의 선량분포를 예측하는데 쓰여질 수 있을 것이다.

• Communications for Statistical Applications and Methods
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• 제18권2호
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• pp.189-199
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• 2011

In this paper, we develop the noninformative priors for the common intraclass correlation coefficient when independent samples drawn from multivariate normal populations. We derive the first and second order matching priors. We reveal that the second order matching prior dose not match alternative coverage probabilities up to the second order and is not a HPD matching prior. It turns out that among all of the reference priors, one-at-a-time reference prior satisfies a second order matching criterion. Our simulation study indicates that one-at-a-time reference prior performs better than the other reference priors in terms of matching the target coverage probabilities in a frequentist sense.

• Radiation Oncology Journal
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• 제8권1호
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• pp.115-124
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• 1990

고 에너지 23MV광자선의 특성 중 임상적용에 중요한 심부선량 백분율, 조직-최대선량비 (TMR), 산란-최대선량비 (SMR), 표면선량 및 출력선량 보정계수등의 변수가 이온전리 (IC-10)함 및 평행 평판전리 (PS-033)함에 의해 측정 조사되었다. 명목상의 23 MV X-선에 대한 가속에너지는 $18.5\pm0.5$ MV로 측정되었다. Mevatron KD 8067의 23 MV X-선의 중심선속의 반가층이 기하학적인 좁은 선속으로 측정되었으며 반가층의 두께는 $24.5\;g/cm^2$이었다. 조직-최대선량비는 심부선량백분율표에서 구해졌으며, 실측치와 비교한 결과 각 조사면의 크기와 깊이에서 약간의 차이를 보였으나 평균 $0.7\pm0.5$의 오차를 나타내고 있어 계산에 의한 TMR 값과 잘 일치함을 보였다. 조사면 $0\times0\;cm^2$의 TMR 값은 zero 조사면의 유효감약계수에 의한 값과, 각 조사면의 조직-최대 선량비로 부터 비선형최소자승법에 의해 구해진 유효선흡수계수 및 반가층 측정에 의한 유효선흡수 계수에 의한 값들로 비교되었으며, $\mu=0.0283{\pm}0,0002cm^{-1}$을 보였고, 세 방법 모두 오차범위내에서 잘 일치됨을 보였다. 한편, 불규칙 조사면의 선량계산에 이용될 SMR은 조사면의 반경 50cm까지 계산되어 대형 조사 면에서도 선량율 산출이 이루어지도록 하였다. Mevatron KD 8067의 23 MV X-선의 조직 표면선량은 SSD 100 cm, 1$10\times10\;cm^2$의 조사면에서 최대조직선량율의 $9.6\%,\;25\times25\;cm^2$에서는 $25.4\%$를 보였다.

• Korean Journal of Radiology
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• 제25권2호
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• pp.179-188
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• 2024

Objective: ¹⁷⁷Lutetium [Lu] Ludotadipep is a novel prostate-specific membrane antigen targeting therapeutic agent with an albumin motif added to increase uptake in the tumors. We assessed the biodistribution and dosimetry of [¹⁷⁷Lu]Ludotadipep in patients with metastatic castration-resistant prostate cancer (mCRPC). Materials and Methods: Data from 25 patients (median age, 73 years; range, 60-90) with mCRPC from a phase I study with activity escalation design of single administration of [¹⁷⁷Lu]Ludotadipep (1.85, 2.78, 3.70, 4.63, and 5.55 GBq) were assessed. Activity in the salivary glands, lungs, liver, kidneys, and spleen was estimated from whole-body scan and abdominal SPECT/CT images acquired at 2, 24, 48, 72, and 168 h after administration of [¹⁷⁷Lu]Ludotadipep. Red marrow activity was calculated from blood samples obtained at 3, 10, 30, 60, and 180 min, and at 24, 48, and 72 h after administration. Organand tumor-based absorbed dose calculations were performed using IDAC-Dose 2.1. Results: Absorbed dose coefficient (mean ± standard deviation) of normal organs was 1.17 ± 0.81 Gy/GBq for salivary glands, 0.05 ± 0.02 Gy/GBq for lungs, 0.14 ± 0.06 Gy/GBq for liver, 0.77 ± 0.28 Gy/GBq for kidneys, 0.12 ± 0.06 Gy/GBq for spleen, and 0.07 ± 0.02 Gy/GBq for red marrow. The absorbed dose coefficient of the tumors was 10.43 ± 7.77 Gy/GBq. Conclusion: [¹⁷⁷Lu]Ludotadipep is expected to be safe at the dose of 3.7 GBq times 6 cycles planned for a phase II clinical trial with kidneys and bone marrow being the critical organs, and shows a high tumor absorbed dose.

• 한국의학물리학회지:의학물리
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• 제11권2호
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• pp.131-139
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• 2000

국내도입 원격제어 근접조사장치인 Ralstron(Shimatsu, Japan) 의 코발트-60선원을 이리디움 192 선원으로 대체하고자 선원을 설계하고, 선원주위의 선량분포를 유도하였다. 이리디움 선원의 물리적크기는 직경1.5mm, 높이 1.5mm 로 370MBq(loci)를 목표로 설계하였으며, 외경은 3mm 이고, 크기는 13m이며, 캡슐의 재질은 SUS316L 이다. 선원 선원자체흡수와 스테인리스 스틸 캡슐에 의한 선량감쇠는 61.2%로 나타났으며, 단위방사능당 감마상수는 4.69R$cm^2$/mCi-hr였다. 조직선량은 공기중흡수선량 변환과 조직산란보정을 통해 구하였으며, 조직흡수선량변환계수는 이리디움의 에너지스펙트럼을 이용하여 공기에 대한 조직의 질량에너지흡수계수비 ($\mu$$_{en}$ )$^{tissue}$ air= 1.112 를 얻었다. 고안 선원에 대한 선량분포는 선원을 2,338개의 선원으로 분할하고, 각 분할선원에서 주위에 도달되는 선량을 이산적으로 누적 평가하여 임상에서 사용할 수 있도록 선량도표를 제공하였다.