• 한국안전학회지
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• 제8권4호
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• pp.165-174
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• 1993

For the safety assessment of the demonstration-scale incineration plant for treating the combustible radioactive wastes, radiation doses of a worker and a residential individual were estimated. The demonstration plant showed a good performance of trial-burn tests using non-radioactive tracers with resulting In high mass reduction of around 40 times and very low emmission of dusts through a stack, which promised a high decontamination factor in an order of 10$^{7}$ . Based on the result s obtained from the trial-burns in the process, the estimation of radiation dose for workers and general publics near the plant was made using dose pathway calculation theories. The parametric values for calculation were selected from design and operational results of the process and from more conservative conditions In reference data. The estimated annual doses for workers and residential indivisuals were 3.07 $\times$ 10$^{-4}$ and 4.35 X 10$^{-8}$ $\mu$Sv/y, respectively, which were high enough to operate the process when comparing with the allowable dose limit in the regulation. The dose calculation models were quite applicable with showing an excellent safety for the process.

• Nuclear Engineering and Technology
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• 제55권1호
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• pp.238-247
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• 2023

The present work represents a technical guideline for decommissioning a disused teletherapy machine model Theratron-780 and contains category one ⁶⁰Co radioactive source. The first section predicts the dose rate from the source in case of normal and radiological emergency situations via FLUKA-MC simulation code. Moreover, the dose assessment for the occupational during the whole process is calculated and compared to the measured values. A suggested cordoned area for safety and security in a radiological emergency is simulated. The second section lists the whole process's technical procedures, including (preview, dismantle, securing, transport and storage) of the disused teletherapy machine. Results show that the maximum obtained accumulated dose for occupational were found to be 24.5 ± 4.9 μSv in the dismantle and securing process in addition to 3.5 ± 1.8 μSv during loading on the transport vehicle and unloading at the storage facility. It was found that the measured accumulated dose for workers is in good agreement with the estimated one by uncertainty not exceeding 5% in normal operating conditions.

• Nuclear Engineering and Technology
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• 제52권8호
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• pp.1784-1791
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• 2020

The 14 MeV neutron generator facility is being developed by the Institute for Plasma Research India to conduct the lab scale experiments related to Indian breeding blanket system for ITER and DEMO. It will also be utilized for material testing, shielding experiments and development of fusion diagnostics. Occupational radiation exposure control is necessary for the all kind of nuclear facilities to get the operational licensing from governing authorities and nuclear regulatory bodies. In the same way, the radiation exposure for the 14 MeV neutron generator facility at the occupational worker area and accessible zones for general workers should be under the permissible limit of AERB India. The generator is designed for the yield of 10¹² n/s. The shielding assessment has been made to estimate the radiation dose during the operational time of the neutron generator. The facility has many utilities and constraints like ventilation ducts, accessible doors, accessibility of neutron generator components and to conduct the experiments which make the shielding assessment challenging to provide proper safety for occupational workers and the general public. The neutron and gamma dose rates have been estimated using the MCNP radiation transport code and ENDF -VII nuclear data libraries. The ICRP-74 fluence to dose conversion coefficients has been used for the assessment. The annual radiation exposure has been assessed by considering 500 h per year operational time. The provision of local shield near to neutron generator has been also evaluated to reduce the annual radiation doses. The comprehensive results of radiation shielding capability of neutron generator building and local shield design have been presented in the paper along with detailed maps of radiation field.

• Journal of Radiation Protection and Research
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• 제36권2호
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• pp.64-70
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• 2011

국내 최초로 국내 원자력 관련 기관을 대상으로 내부피폭방사선량 상호비교 프로그램을 실시하여 국내 내부선량 평가결과의 조화성을 분석하였다. 이를 위하여 섭취경로, 흡수형태, 방사능 입자크기(AMAD) 및 섭취시점을 모르는 경우에 대한 내부선량 평가문제를 개발하였으며, 세 종류의 문제에 각 세 문항씩 총 9문항을 제시하였다. 이번 상호비교 프로그램에는 원자력의학원, 방사선보건연구원, 원자력발전소(고리, 영광, 울진)의 내부선량평가 담당자 7명이 참가하여 문제에 대한 답안을 제출하였으며, 각 문제별 참가자 답안의 기하평균에 대한 각 참가자 답안의 상대 비 분포는 $5.75{\times}10^{-4}$ ~ 9.81이었고, 평가과정에서 극히 일부의 답안을 제외할 경우 참가자 답안의 기하평균에 대한 각 참가자 답안의 상대 비는 0.216 ~ 3.12의 분포를 보였다.

• 대한방사선기술학회지:방사선기술과학
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• 제40권1호
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• pp.49-55
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• 2017

의료기관 내 핵의학 종사자는 방사성동위원소 취급 시 사용하는 선원의 종류, 방사능량, 차폐기구의 사용 여부에 따라 종사자 개인별로 광범위한 피폭선량을 나타낼 수 있다. 이에 본 연구에서는 몬테카를로 기법을 기반으로 한 모의실험을 통해 진단용 방사선원 취급 시 종사자의 장기별 선량평가와 L-block 차폐기구 사용에 따른 선량감소효과를 분석하였다. 그 결과, 방사선원의 취급 위치에 근접할수록 높은 장기선량 분포를 나타내었고, ICRP 조직가중치에 따라 유효선량 분포가 상이한 양상을 보였다. 또한 L-block 두께에 따른 선량감소효과는 차폐두께 증가에 따라 지수함수 분포로 감소되는 경향을 나타내었으며, 방사선원별 선량감소효과는 방출하는 감마선 에너지에 비례하여 낮은 차폐효과를 보였다.

• Journal of Radiation Protection and Research
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• 제43권2호
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• pp.50-58
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• 2018

Background: In terms of the Level 3 probabilistic safety assessment (Level 3 PSA), ingestion of food that had been exposed to radioactive materials is important to assess the intermediate- and long-term radiological dose. Because the ingestion dose is considerably dependent upon the agricultural and dietary characteristics of each country, the reliability of the assessment results may become diminished if the characteristics of a foreign country are considered. Thus, this study intends to evaluate and analyze the ingestion dose of Korean during a severe accident by completely considering the available agricultural and dietary characteristics in Korea. Materials and Methods: This study uses COMIDA2, which is a program based on dynamic food chain model. It sets the parameters that are appropriate to Korean characteristics so that we can evaluate the inherent ingestion dose of Korean. The results were analyzed by considering the accident date and food category with regard to the $^{137}Cs$. Results and Discussion: The dose and contribution of the food category depicted distinctive differences based on the accident date. Particularly, the ingestion dose during the first and second years depicted a considerable difference by the accident date. However, after the third year, the effect of foliar absorption was negligible and exhibited a similar tendency along with the order of root uptake rate based on the food category. Conclusion: In this study, the agricultural and dietary characteristics of Korea were analyzed and evaluated the ingestion dose of Korean during a severe accident using COMIDA2. By considering the inherent characteristics of Korean, it can be determined that the results of this study will significantly contribute to the reliability of the Level 3 PSA.

• 한국수학교육학회지시리즈C:초등수학교육
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• 제3권2호
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• pp.143-149
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• 1999

The Assessment using the observation is one of the common ways to know what the student knows and dose not. Using the obserbational Assessment, Teachers, analyzing student's growth, provide appropriate feed-back, and so they try to record every activities. but, accumulatively recording the result of observational assessment face time·spacial limits. and it is difficult to apply in a real classroom situation. Taking these into consideration, I'd like to take a look at the idea of check-list assessment that could record data observing student and contrive a practical ways of application.

• Toxicological Research
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• 제6권2호
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• pp.205-213
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• 1990

The regulation of neurotoxicants has usually been based upon setting reference doses by dividing a no observed adverse effect level (NOAEL) by uncertainty factors that theoretically account for interspecies and intraspecies extraploation of experimental results in animals to humans. Recently, we have proposed a four-step alternative procedure which provides quantitative estimates of risk as a function of dose. The first step is to establish a mathematical relationship between a biological effect or biomarker and the dose of chemical administered. The second step is to determine the distribution (variability) of individual measurements of biological effects or their biomarkers about the dose response curve. The third step is to define an adverse or abnormal level of a biological effect or biomarker in an untreated population. The fourth and final step is to combine the information from the first three steps to estimate the risk (proportion of individuals exceeding on adverse or abnormal level of a biological effect or biomarker) as a function of dose. The primary purpose of this report is to enhance the certainty of the first step of this procedure by improving our understanding of the relationship between a biomarker and dose of administered chemical. Several factors which need to be considered include: 1) the pharmacokinetics of the parent chemical, 2) the target tissue concentrations of the parent chemical or its bioactivated proximate toxicant, 3) the uptake kinetics of the parent chemical or metabolite into the target cell(s) and/or membrane interactions, and 4) the interaction of the chemical or metabolite with presumed receptor site(s). Because these theoretical factors each contain a saturable step due to definitive amounts of required enzyme, reuptake or receptor site(s), a nonlinear, saturable dose-response curve would be predicted. In order to exemplify this process, effects of the neurotoxicant, methlenedioxymethamphetamine (MDMA), were reviewed and analyzed. Our results and those of others indicate that: 1) peak concentrations of MDMA and metabolites are ochieved in rat brain by 30 min and are negligible by 24 hr, 2) a metabolite of MDMA is probably responsible for its neurotoxic effects, and 3) pretreatment with monoamine uptake blockers prevents MDMA neurotoxicity. When data generated from rats administerde MDMA were plotted as bilolgical effect (decreases in hippocampal serotonin concentrations) versus dose, a saturation curve best described the observed relationship. These results support the hypothesis that at least one saturable step is involved in MDMA neurotoxicity. We conclude that the mathematical relationship between biological effect and dose of MDMA, the first step of our quantitative neurotoxicity risk assessment procedure, should reflect this biological model information generated from the whole of the dose-response curve.

• 한방재활의학과학회지
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• 제31권1호
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• pp.95-108
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• 2021

Objectives This study was conducted to investigate the beta-glucan, ginsenoside content, antioxidant activity and safety of modified Kyungohkgo added to Sparassis crispa and Hericium erinaceum. Methods The marker compounds contents, antioxidant activity and safety of modified Kyungohkgo were tested. The contents of beta-glucan and ginsenoside Rb1, Rg1, and Rg3 marker compounds were measured, the antioxidant activity was measured using 2,2-diphenyl-1-picrylhydrazyl (DPPH) free radical scavenging activity, and a safety test was conducted via single dose toxicity assessment. Results Analyzing the contents of marker compounds showed 351.75 mg/g of beta-glucan, 0.0327 mg/g of ginsenoside Rb1 and 0.0802 mg/g of ginsenosai Rg3. In the DPPH free radical scavenging activity, the inhibition concentration 50% of modified Kyungohkgo was 0.2880%. The scavenging activity of modified Kyungohkgo was 5.49% activity at 0.05% concentration, 89.66% activity at 0.5% concentration, 94.68% activity at 1% concentration, and 96.06% activity at 5% concentration. In the single dose toxicity test of modified Kyungohkgo, a dose of 2,000 mg/kg B.W. was set at its highest capacity and observed after oral administration to female and male rats. No toxicological findings were recognized. It was observed that the resulting lethal dose can be set to 2,000 mg/kg B.W. or higher for both females and males. Conclusions The results of the experiment on modified Kyungohkgo showed that the marker compounds contents were beta-glucan and ginsenoside Rb1 and Rg3, that antioxidant activity was observed through the DPPH free radical scavenging activity, and safety was confirmed through the single dose toxicity assessment.

• 대한한의학회지
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• 제30권6호
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• pp.27-34
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• 2009

Objectives: To evaluate the acute toxic effects and approximate lethal dose of Cheonggan extracts (CGX) in SD rats and beagle dogs. Methods: Male and female rats were divided into 4 groups (Control, CGX 1250, CGX 2500, CGX 5000) respectively and male and female dogs were divided into two groups respectively (Control, CGX 5000) respectively. A single oral dose of CGX was treated to the rats and dogs. Mortality, signs of gross toxicity, and behavioral changes were observed over 14 days. All animals were observed every hour for 4 hours after administration and once a day thereafter for 14 days. Body weights were determined at $0_{th}$, $7_{th}$, and $14_{th}$ days. All surviving animals were sacrificed and necrotized. Major organs were inspected visually for gross findings. Results: No animals died in any of the groups during the experimental period (2 weeks), rats or dogs. Body weights of rats and dogs during the experiment continuously increased in all groups but there was no significant change. No abnormal clinical signs were observed for 2 weeks after a single administration of CGX in any dose group of CGX, rats or dogs. No abnormal findings in major organs were observed in any group of rats or dogs. Conclusion: CGX does not have acute toxic effects in rats or dogs. Therefore, an approximate lethal dose is assumed to exceed 5000 mg/kg in both rats and dogs.