• International Journal of Contents
• /
• 제16권2호
• /
• pp.102-108
• /
• 2020

The purpose of this study was to estimate and analyze the potential radiation dose that the future visitors and the cleaning staff will be exposed to when the KRR-1 reactor is converted into a memorial hall. The radiation doses were estimated using the RESRAD-BUILD software, where case, building, receptor, shielding, and source parameters were applied as the input data. Also, the basic data for the assessment of the radiation doses were determined in an indirect manner using the data on the waste generated during the decommissioning process of the reactor. The assessment results indicate that the potential radiation dose to the visitors and the cleaning staff will be less than 1 mSv, the annual dose limit for the general public. However, if anyone for a significant period of time is close to the reactor, the overall dose will increase. The radiation dose for the future visitors and the cleaning staff was determined to be lower than the annual dose limit for the general public. Given such a risk, systematic measures, such as periodic monitoring or limiting hours, are imperative.

• 대한방사선기술학회지:방사선기술과학
• /
• 제42권2호
• /
• pp.131-135
• /
• 2019

The purpose of this study was to evaluate the efficacy of brachytherapy of breast cancer by dose assessment which a steady increased in Korea women. The dose assessment was performed using the MCNPX program, a MonteCarlo simulation technique. The sources used for brachytherapy was 192Ir. And nanoparticle which used for dose enhancement was gold. The density of nanoparticle was 7, 18 and 30 mg. Evaluation of absorbed dose according to distance is measured at a distance of 30, 50, 100 and 200 cm from the patient. As a result, The breast absorbed dose results increased in proportion to the density of nanoparticle. And the surrounding organs were not significantly different according to the density. But, in some organs, the absorbed dose decreased as the density of nanoparticles increased. Absorbed dose according to the distance was in inverse proportion to distance.

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

• Asian Pacific Journal of Cancer Prevention
• /
• 제16권18호
• /
• pp.8553-8557
• /
• 2016

Background: Accurate dose assessment and correct identification of irradiated from non-irradiated people are goals of biological dosimetry in radiation accidents. Objectives: Changes in the FDXR and the RAD51 gene expression (GE) levels were here analyzed in response to total body exposure (TBE) to a 6 MV x-ray beam in rats. We determined the accuracy for absolute quantification of GE to predict the dose at 24 hours. Materials and Methods: For this in vivo experimental study, using simple randomized sampling, peripheral blood samples were collected from a total of 20 Wistar rats at 24 hours following exposure of total body to 6 MV X-ray beam energy with doses (0.2, 0.5, 2 and 4 Gy) for TBE in Linac Varian 2100C/D (Varian, USA) in Golestan Hospital, in Ahvaz, Iran. Also, 9 rats was irradiated with a 6MV X-ray beam at doses of 1, 2, 3 Gy in 6MV energy as a validation group. A sham group was also included. After RNA extraction and DNA synthesis, GE changes were measured by the QRT-PCR technique and an absolute quantification strategy by taqman methodology in peripheral blood from rats. ROC analysis was used to distinguish irradiated from non-irradiated samples (qualitative dose assessment) at a dose of 2 Gy. Results: The best fits for mean of responses were polynomial equations with a R2 of 0.98 and 0.90 (for FDXR and RAD51 dose response curves, respectively). Dose response of the FDXR gene produced a better mean dose estimation of irradiated "validation" samples compared to the RAD51 gene at doses of 1, 2 and 3 Gy. FDXR gene expression separated the irradiated rats from controls with a sensitivity, specificity and accuracy of 87.5%, 83.5% and 81.3%, respectively, 24 hours after dose of 2 Gy. These values were significantly (p<0.05) higher than the 75%, 75% and 75%, respectively, obtained using gene expression of RAD51 analysis at a dose of 2 Gy. Conclusions: Collectively, these data suggest that absolute quantification by gel purified quantitative RT-PCR can be used to measure the mRNA copies for GE biodosimetry studies at comparable accuracy to similar methods. In the case of TBE with 6MV energy, FDXR gene expression analysis is more precise than that with RAD51 for quantitative and qualitative dose assessment.

• 방사성폐기물학회지
• /
• 제2권1호
• /
• pp.60-67
• /
• 2004

연구로 1,2호기 해체과정에서 발생되는 많은 양의 철재폐기물 중 자체처분대상 철재폐기물을 대상으로 재활용하는 경우에 대해서 피폭방사선량을 평가하고, 규제해제농도기준(안)을 도출하였다. 평가도구는 RESRAD-RECYCLE ver 3.06을 이용하여 ICRP60에서 제시하고 있는 유효선량 개념에 근거한 내부피폭 선량환산인자를 수정하였고, IAEA Safety Series 111-P-1.1 및 NUREG-1640을 적용하여 예상되는 최대개인선량 및 집단선량을 평가하였다. 0.4 Bq/g의 철재폐기물에 대한 RESRAD-RECYCLE 전산코드의 평가결과 개인최대선량 및 집단선량은 23.9 $\mu$Sv/y, 0.11 man$.$Sv/y이다. 최종적인 핵종별 규제해제농도기준은 일반평가방법과 세부평가결과를 종합하여 가장 보수적인 평가결과를 추출하여 결정하였다. 그 결과 $Co^{60}$, C $s^{137}$ 핵종에 대한 규제해제농도준위는 1.14${\times}$$10^{-1}$ Bq/g미만이 되어야 국내 원자력법에서 정하고 있는 처분제한치(최대개인선량 : 10 $\mu$Sv/y, 집단선량 : 1 man$.$Sv/y)를 만족할 수 있다.

• 생명과학회지
• /
• 제26권10호
• /
• pp.1153-1162
• /
• 2016

계종버섯(Thermitomyces albuminosus)의 안정성을 입증하기 위하여 사료에 계종버섯의 분말을 5%, 2.5%, 1.25%, 0%를 혼합하여 90일 동안 랫드에 자유 급이 시켜 실험동물의 일반증상, 체중변화, 혈액학적 검사, 부검소견, 임상병리, 조직병리학적 검사의 결과를 토대로 독성을 평가하였다. 독성판정기준은 독성의 정도와 양상에 따라 weight-based classification (독성 강도에 따른 분류)로 분류 하였는데 비시험물질-유래 변화인 NOEL, 시험물질-유래 경미한 변화는 NOAEL, 시험물질-유래 중요한 변화는 LOAEL을 기준으로 나누었다. 시험결과, 수컷 좌, 우측 신장 중량이 용량의존적으로 증가하여 고용량군에서는 12%, 8% 증가 하였다. 하지만 임상, 조직병리학적 결과 독성으로 판단되는 소견이 관찰되지 않아 시험물질-유래 경미한 변화로 판단으로 분류하였다. 따라서 판정기준에 따라 수컷은 NOAEL 암컷은 NOEL이 식이함량 5%로 추정되지만 식약처고시에 따라 암수 모두 NOAEL이 식이함량의 5%로 추정할 수 있다. 따라서 계종버섯은 식품 또는 기능성식품으로의 개발에 문제가 없을 것으로 사료된다.

• Journal of Radiation Protection and Research
• /
• 제35권4호
• /
• pp.142-150
• /
• 2010

중수로 사용후핵연료의 처분 효율을 높이기 위하여 새롭게 제안된 처분 시스템에 대한 방사선량을 MCNPX를 사용하여 계산함으로써 이 시스템의 방사선 안전성을 예비적으로 평가하고자 하였다. 이를 위해서 처분시스템의 각 요소에 대한 구성, 제원, 재질 등을 분석하였으며, 그에 상응하는 모델링을 수행하였다. 선량평가는 주요 구성요소에 대하여 수행하였으며, 평가결과 내부 구성요소에 대해서는 방사선량이 높은 편이었으나, 최종적인 처분시스템은 방사선에 대한 안전성이 높은 것으로 나타났다.

• 한국한의학연구원논문집
• /
• 제2권1호
• /
• pp.129-145
• /
• 1996

According to the Medical Product Safety Administration Guidelines for safety assessment guinea pigs, mice and rats were used for antigenicity test, rabbits for pyrogenic test and hymolytic test. The results were summarized as follows; 1. The antigenicity test of Red-ginseng radix extract solution for herb-acupuncture did not show any anaphylatic shock but produced IgE in high dose group. 2. The result of the pyrogen test of Red-ginseng radix extract solution for herb-acupuncture was negative. 3. The result of the hemolytic test of Red-ginseng radix extract solution for herb-acupuncture were negative in low and middle dose group but was positive in high dose group.

• Journal of Radiation Protection and Research
• /
• 제43권2호
• /
• pp.39-49
• /
• 2018

Background: A model to assess the activity concentration of agricultural products and the public ingestion dose as result of a nuclear accident is necessarily required to manage the contaminated agricultural systems by the accident, or to estimate the effects of chronic exposure due to food ingestion at a Level 3 PSA. Materials and Methods: A dynamic compartment model, which is composed of three sub-modules, namely, an agricultural plant contamination assessment model, an animal product contamination assessment model, and an ingestion dose assessment model has been developed based on Korean farming characteristics such as the growth characteristics of rice and stockbreeding. Results and Discussion: The application study showed that the present model can predict well the characteristics of the activity concentration for agricultural products and ingestion dose depending on the deposition date. Conclusion: The present model is very useful to predict the radioactivity concentration of agricultural foodstuffs and public ingestion dose as consequence of a nuclear accident. Consequently, it is expected to be used effectively as a module for the ingestion dose calculation of the Korean agricultural contamination management system as well as the Level 3 PSA code, which is currently being developed.

• 방사성폐기물학회지
• /
• 제6권2호
• /
• pp.73-100
• /
• 2008

고준위 방사성폐기물 처분장으로부터 유출된 핵종에 의한 선량률을 계산하기 위한 생태계평가 코드 ACBIO를 일반적인 구획모델링도구인 AMBER를 이용하여 BIOMASS 방법론을 적용하여 개발하였다. ACBIO의 유용성을 보이고, 구획의 변화나 일부 파라미터값의 변화에 따른 구획 내 농도와 방사능, 그리고 구획간의 플럭스의 민감도도 검토하였다. 지하매질-생태계 경계(GBI)를 통해 넘어오는 핵종의 유출플럭스에 따른 선량환산인자를 각 핵종별로 구하여 결정집단내 개인의 최대피폭선량율을 선량환산인자로 얻는 계산을 수행하였다. 또한 생태계 요소의 구획모델링이나 가능한 피폭집단의 설정, 그리고 GBI의 인지 등이 생태계평가에 중요한 요소가 되는 것을 확인하였다.