Earticle

While high-dose ionizing radiation results in long term cellular cytotoxicity, chronic low-dose (<0.2 Gy) of X- or γ-ray irradiation can be beneficial to living organisms by inducing radiation hormesis, stimulating immune function, and adaptive responses. During chronic low-dose-rate radiation (LDR) exposure, whole body of mice is exposed to radiation, however, it remains unclear if LDR causes changes in gene expression of the whole brain. Therefore, we aim to investigate expressed genes (EGs) and signaling pathways specifically regulated by LDR-irradiation (137Cs, a cumulative dose of 1.7 Gy for total 100 days) in the whole brain. Using microarray analysis of whole brain RNA extracts harvested from ICR and AKR/J mice after LDR- irradiation, we discovered that two mice strains displayed distinct gene regulation patterns upon LDR-irradiation. In ICR mice, genes involved in ion transport, transition metal ion transport, and developmental cell growth were turned on while, in AKR/J mice, genes involved in sensory perception, cognition, olfactory transduction, G- protein coupled receptor pathways, inflammatory response, proteolysis, and base excision repair were found to be affected by LDR. We validated LDR-sensitive EGs by qPCR and confirmed specific upregulation of S100a7a, Olfr624, and Gm4868 genes in AKR/J mice whole brain. Therefore, our data provide the first report of genetic changes regulated by LDR in the mouse whole brain, which may affect several aspects of brain function.

본 연구에서는 미래 파이로 시설에서의 핵물질 계량 연구를 위하여 개발하고 있는 통합비파괴측정장치(Unified Non-Destructive Assay, UNDA)의 중성자 검출 효율을 MCNPX 코드를 이용하여 평가하였다. 검출 효율 평가는 두 개의 다른 설계안의 UNDA에 대하여 수행되었으며, 252Cf 중성자 발생 선원 위치에 따른 검출 효율 평가와 감손우라늄 의 용기 두께 및 위치에 따른 검출 효율 평가를 수행하였다. 252Cf 중성자 선원의 위치에 따른 UNDA의 검출 효율 결과는 6.83%부터 13.35%까지 분포로 나타났으며, 252Cf 선원이 장치 내부의 상단에 위치할수록 검출 효율은 증가 후 감소하는 경향을 나타냈고, 선원이 외각에 위치될수록 효율이 증가하는 경향을 보였다. 감손우라늄 용기의 두께 및 위치에 따른 검출 효율 평가에서는 용기 두께가 증가할수록 검출 효율은 낮아지는 경향을 보이며, 용기 위치가 장치 상부에 위치될수록 효율은 감소하고, 외각에 위치할수록 효율은 증가하였다. 검출 효율은 252Cf 선원의 경우보다 약간 높게 나타났다(10.31~13.61%). 또한, 장치 상단에 고밀도 폴리에틸렌 덮개가 있는 설계안이 덮개가 없는 설계안 보다 평균적으로 약 2% 정도 중성자 검출 효율이 높은 것으로 평가되었다.

In this study, neutron detection efficiency of the UNDA system, which has been developed for study on nuclear material accountancy in a future pyro-process facility, was evaluated by using the MCNPX code. The detection efficiency was evaluated as a function of (1) positions of 252Cf neutron source in the axial and radial directions, and (2) thicknesses and locations of the container filled with the depleted uranium materials for two different designs of the UNDA. In the case of 252Cf source positions, detection efficiency was distributed from 6.83% to 13.35%. As 252Cf source was positioned at upper part in the axial direction, detection efficiency was decreased after a slight increase. On the other hands, as 252Cf source was positioned at outer part in the radial direction, detection efficiency was increased. In the case of container thickness, there was a slight decline when the thickness was increased. As the container was located at upper part, detection efficiency was decreased and as the container was located at outer part, detection efficiency was increased. Detection efficiency was varied from 10.31% to 13.61%. These values were higher than that of 252Cf source case. The UNDA with polyethylene cover has about 2% higher detection efficiency than the UNDA without the cover.

The biological effects of radiation are dependent on the dose rate and dose of radiation. In this study, effects of dose and dose rate using whole body radiation on plasma cytokines and blood count from male BALB/c mice were evaluated. We examined the blood and cytokine changes in mice exposed to a low (3.49 mGy h-1) and high (2.6 Gy min-1) dose rate of radiation at a total dose of 0.5 and 2 Gy, respectively. Blood from mice exposed to radiation were evaluated using cytokine assays and complete blood count. Peripheral lymphocytes and neutrophils decreased in a dose dependent manner following high dose rate radiation. The peripheral lymphocytes population remained unchanged following low dose rate radiation; however, the neutrophils population increased after radiation. The sera from these mice exhibited elevated levels of flt3 ligand and granulocyte-colony-stimulating factor (G-CSF), after high/low dose rate radiation. These results suggest that low-dose-rate radiation does not induce blood damage, which was unlike high-dose-rate radiation treatment; low-dose-rate radiation exposure activated the hematopoiesis through the increase of flt3 ligand and G-CSF.

Heating method using electric heater was used to reduce water content in fingernail clippings. Authors found that low water content is helpful to measure EPR signal of fingernail sample with enhanced variability. Generally, natural dehydration happens in normal room condition at least one month and needs much time for using in experiment. So, artificial heating method is applied in this study for time savings. Fingernail samples were tested to find effect of water content to the EPR signal on microwave power levels for dosimetry. Low water content in fingernail reduced variability of EPR signal and makes it possible to measure accurate EPR signal. It also made it possible to measure constant movement of EPR signals on several microwave power levels. Although this method was difficult to apply directly in fingernail/EPR dosimetry, we, authors, believe that this heating method would be useful to differentiate MIS2 and RIS which are generally located at the same g-factor and almost impossible to be identified with each other.

경수로 사용후핵연료 건식 중간저장시설 격납건물 크기에 따른 방사선량률 추이 분석을 위하여 격납건물 외부 벽면에 서의 추정연간선량을 계산하였다. ORIGEN-ARP를 사용하여 농축도 4.5 wt%, 연소도 45,000 MWd/MTU 냉각기간 10 년인 사용후핵연료를 대상으로 선원항을 생산하였으며, MCNP 코드를 사용하여 저장시설 및 격납건물에 대한 모델링 및 선량률 계산을 수행하였다. 연간선량은 격납건물 외부 벽면에서의 값으로 계산하였으며, 격납건물 벽과 최외곽 배 열의 저장용기와의 간격을 50 m 이상으로 설정할 경우 10CFR72에서 제시하는 연간선량인 0.25 mSv 이하의 값이 계산되었다.

Annual dose on the containment building wall of the interim storage facility at normal condition was calculated to estimate the dose rate transition of the facility of PWR spent nuclear fuel. In this study, source term was generated by ORIGEN-ARP with 4.5 wt% initial enrichment, 45,000 MWd/MTU burnup and 10 years cooling time. Modeling of the storage facility and the containment building and radiation shielding evaluations were conducted by MCNP code depending on the distance between the wall and the facility in the building. In the case of the centralized storage system, the distance required for the annual dose rate limit from 10CFR72 was estimated to be 50 m.

To investigate monitoring unit (MU) efficiency and plan quality of volumetric modulated arc therapy (VMAT) using flattening-filter free (FFF) photon beam in association with target size and location. A virtual patient was generated in EclipseTM (ver. A10, Varian Medical Systems, Palo Alto, USA) treatment planning system. The length of major and minor axis in axial view was 50 cm and 30 cm, respectively. Cylindrical-shaped targets were generated inside that patient at the center (symmetric target) and in the periphery (asymmetric target, 7.5 cm away from the center of the patient to the right direction) of the virtual patient. The longitudinal length was 10 cm and the diameters were 2, 5, 10 and 15 cm. Total 8 targets were generated. RapidArcTM plans using TrueBeam STxTM were generated for each target. Two full arcs were used and the axis of rotation of the gantry was set to be at the center of the virtual patient. Total MU, homogeneity index (HI), target mean dose, the value of gradient measure and body mean dose were calculated. In the case of symmetric targets, averaged total MU of FFF plan was 23% and 19% higher than that of flattening filter (FF) plan when using 6 MV and 10 MV photons, respectively. The difference of HI, target mean dose, gradient measure and body mean dose between FF and FFF was less than 0.04, 2.6%, 0.1 cm and 2.2%, respectively. For the asymmetric targets, total MU of FFF plan was 21% and 32% was higher than that of FF when using 6 MV and 10 MV photons, respectively. The homogeneity of the target was always worse when using FFF than using FF. The maximum difference of HI was 0.22. The target mean dose of FFF was 3.2% and 4.1% higher than that of FF for the 6 MV and 10 MV, respectively. The difference of gradient measure was less than 0.1 cm. The body mean dose was higher when using FFF than FF about 4.2% and 2.8% for the 6 MV and 10 MV, respectively. No significant differences between VMAT plans of FFF beam and FF beam were observed in terms of quality of treatment plan. The HI was higher when using FFF 10 MV photons for the asymmetric targets. The MU was increased noticeably when using FFF photon beams.

생체 조직의 전기 신호는 살아 있는 조직과 관련된 많은 정보를 포함하고 있으며, 생체 조직에 생물학적 변화가 있으면 고유의 전기적 특성이 변화한다. Impedance/Gain-phase analyzer로 1 ㎑ 에서 1 ㎒ 까지 주파수 대역을 설정한 다음 교류 주파수를 인가하며 돼지안심 조직의 임피던스 특성을 방사선 피폭선량에 따라 변화가 있는지 알아보고자 하였다. 임피던스 크기는 주파수에 비례하여 감소하였으며, 상관계수(r)가 -0.96으로 높은 음의 상관관계를 보였다. 위상차 변 화는 거의 없었으며 조직은 저항성을 나타내었다. 측정값은 변동계수가 ±5%이내로 재현성이 있음을 알 수 있었고, 측정 시간 경과에 따른 임피던스 크기와 위상차 변화는 유의적인 차이가 없었다.(p>0.05) 방사선 피폭 시 임피던스 변화는 대조군과 비교했을 때 1 ㏉, 2 ㏉, 4 ㏉ 피폭 선량에서는 임피던스 크기는 감소하였으나, 유의적인 차이는 없었 다.(p>0.05) 그러나 10 ㏉ 피폭 선량에서는 임피던스 크기 감소가 유의적으로 나타났다.(p<0.05) 방사선 피폭선량이 증가하여도 위상차 변화는 거의 없었으며, 대조군과 비교했을 때 1 ㏉, 2 ㏉, 4 ㏉, 10 ㏉ 모두 유의적인 차이가 없었 다.(p>0.05) 본 연구를 통해 생체 조직의 전기적 특성을 이해 할 수 있었고, 방사선 피폭선량에 따른 임피던스 변화를 측정하여 방사선이 인체에 미치는 영향을 직접 평가 할 수 있는 가능성을 확인 할 수 있었다.

Bioimpedance involves a lot of information related to living tissue. If there is alteration in bio tissue, its electrical characteristics also change. It is to study electrical characteristics of pork tenderlion in using a HP-4194A Impedance/ Gain-phase analyzer instrument and electrical characteristics changes by graded radiation exposure dose. The results were as follow 1. Electrical characteristics of pork tenderlion in repeated measurement had high precision within ±5% of coefficiency of variability. 2. During the measurement impedance absolute value and phase alteration did not show statistically significant difference.(p>0.05) 3. While impedance phase of electrical characteristics associated with frequency change was almost stable, impedance absolute value was in inverse proportion to frequency that means high inverse correlation of -0.096(r). 4. Impedance absolute value dropped in radiation exposure dose. The alteration of the value did not show statistically significant difference in 1 ㏉, 2 ㏉ and 4 ㏉.(p>0.05) However in radiation exposure dose of 10 ㏉, the decrease of impedance absolute value was significantly different.(p<0.05) 5. Impedance phase according to radiation exposure dose change did not show statistically significant difference in 1 ㏉, 2 ㏉, 4 ㏉, and 10 ㏉.(p>0.05)

원전의 안전성분석보고서에는 운영기간중 만일의 사고에 따른 방사선안전성 확보를 위해 부지의 적합성 평가가 요구 된다. 부지 적합성은 극히 보수적인 가정을 적용하여 제한구역경계에서 방사선 피폭영향을 평가하여 판단하게 된다. 이들 평가는 방사선영향평가 모델을 보수적인 기상조건 등에 적용하여 수행된다. 본 연구에서는 보수적인 평가 결과의 타당성 검증을 목적으로 확산에 양호하지 못한 악기상 조건에서 추적자확산실험을 실시하였다. 원전부지 실험에 앞서 대전시 인근 유성구 학하리 평지에서 추적자 확산실험을 실시하였다. 확산실험의 분석결과 기존의 확산조건이 좋은 경우의 실험결과와 비교할 때 크게 두 가지 큰 차이를 발견할 수 있었다. 하나는 풍속이 매우 낮고 풍향의 변화가 심해 주 풍하 방향에서 나타나는 최대 농도를 찾기 어렵다는 것이고, 다른 하나는 대기가 매우 안정하여 지상 10 m 낮은 높이에서의 방출임에도 불구하고 방출점에서 수 백 m 떨어진 지점에서 처음으로 상대적으로 높은 농도 분포가 나타나는 경우가 있다는 것이다.

The suitability of the site criteria is a basic requirement for securing safety of nuclear power plants. The suitability should be confirmed through the estimation of environmental radiation effects at the exclusion area boundary under the severe weather conditions. In this study, field tracer experiments over short range of 1 km radius under severe weather conditions were conducted at flat area in Daejeon. Severe weather conditions are represented with stable atmospheric condition and low wind speed. In general, the condition is appeared at clean night time with weak wind. The analysis of the measured distribution of the released tracer gas shows two big differences between the results of the past experiments conducted under the favorable weather conditions. One is the difficulty of finding the typical distribution of the released tracer gas with peak concentration in the downwind direction. The other one is the appearance of the contour of the concentration of tracer gas at several hundred meters even though the gas released at 10 m height over the ground.

MDCT의 등장과 함께 병적 증상이 없는 개인이 조기검진을 위해 CT검사를 하는 예가 꾸준히 증가하고 있다. 이러한 검사의 임상적 효용성과 방사선에 의한 암 발생위험에 대한 여러 가지 논란을 살펴보았다. 1. 저선량흉부CT(LDCT)를 이용한 폐암의 조기 검진 효용성을 보기 위해 설계된 무작위배정대조검사(randomized controlled trial)인 NLST(National Lung Screening Trial)의 분석 결과, CT선별검사가 선별검사를 하지 않은 그룹의 사망률 1.67%를 1.33%로, 20% (p=0.004) 감소시키는 것으로 나타났다. CT선별검사군에서 양성결과를 보인 사람 의 96.4%는 위양성(false-positive)이었다. 그리고 방사선에 의한 폐암의 ERR (excess radiation risk)은 다른 고형암 과는 달리 나이와 함께 감소하지 않으며, 더욱이 흡연 위험과 방사선 위험이 상승작용을 하여 폐암 검진 대상인 고위험군에게 더욱 위험할 수 있는 것으로 평가되었다. 따라서 방사선에 의한 위험이 NLST에서 관측한 이득을 상 쇄할 수도 있다. 아직은 최적의 전략이 확립되지 않은 상태이므로 임상에서 광범위하게 적용하기에는 한계가 있다. 2. 대장CT검사(CT colonography)는 10 mm보다 큰 용종의 검출에는 정확도가 뛰어나지만 이보다 작은 경우에는 민감 도와 특이도가 급격히 감소하고, 용종이 발견되어 제거하고자 하는 경우 다시 기존의 대장내시경을 이용해야 하는 불편함이 있다. 현재 대장CT검사 1회 시행의 평균유효선량은 약 8-10  로 보고되어, 만약 이 검사가 많은 사람 들을 대상으로 일상적으로 행해지면 공중보건에 영향을 미칠 수 있다. 따라서 집단검진 방법으로 정착하기 위해서 는 용종 크기 6-10 mm 범위에서 높은 민감도와 특이도를 확립하고, 하제를 사용하지 않는 방법을 개발하여야 하며, 선량을 더 감소시킬 수 있는 최적화된 전략을 세워 표준화하여야만 한다. 3. 전신CT검사는 그 효용성이 검증된 선행연구가 없는 상태이다. 이 검사는 약 90%의 검사자들에게서 최소한 하나 이상의 이상소견을 확인하였지만 그 중 약 2%만이 임상적으로 중요한 질환으로 판명되었다. 전신CT검사 1회 시행 으로 인한 평균유효선량은 약 12   이며 45세부터 75세까지 매년 검사를 받는 경우 LAR (lifetime attributable risk)이 1.9%로 보고되었다. 현재 의학계의 어떤 단체도 이 검사를 권고하고 있지 않다. 현재까지 CT선별검사는 정당화에 대한 충분한 논의를 위해 심도 있는 다양한 연구가 필요하며 최적화된 프로토콜이 확립된 후 이용하는 것이 바람직하다.

Computed tomographic scan as a screening procedures in asymptomatic individuals has seen a steady increase with the introduction of multiple-raw detector CT scanners. This report provides a brief review of the current controversy surrounding CT cancer screening, with a focus on the radiation induced cancer risks and clinical efficacy. 1. A large study of patients at high risk of lung cancer(the National Lung Screening Trial[NLST]) showed that CT screening reduced cancer deaths by 20%(1.33% in those screened compared with 1.67% in those not screened). The rate of positive screening tests was 24.2% and 96.4% of the positive screening results in the low-dose CT group were false- positive. Radiation induced lung cancer risk was estimated the most important in screening population because ERR of radiation induced lung cancer does not show the decrease with increasing age and synergistic connection between smoking and radiation risk. Therefore, the radiation risk may be on the same order of magnitude as the benefit observed in the NLST. Optimal screening strategy remain uncertain, CT lung cancer screening is not yet ready for implementation. 2. Computed tomographic colonography is as good as colonoscopy for detecting colon cancer and is almost as good as colonoscopy for detecting advanced adenomas, but significantly less sensitive and specific for smaller lesions and disadvantageous for subsequent therapeutic optical colonoscopy if polyps are detected. The average effective dose from CT colonography was estimated 8-10 , which could be a significant dose if administered routinely within the population over many years. CT colonography should a) achieve at least 90% sensitivity and specificity in the size category from 6 and 10 mm, b) offer non-cathartic bowl preparation and c) be optimized and standardized CT parameters if it is to be used for mass screening. 3. There is little evidence that demonstrates, for whole-body scanning, the benefit outweighs the detriment. This test found large portion of patient(86~90.8%) had at least one abnormal finding, whereas only 2% were estimated to have clinically significant disease. Annual scans from ages 45 to 75 years would accrue an estimated lifetime cancer mortality risk of 1.9%. There is no group within the medical community that recommends whole-body CT. No good studies indicate the accuracy of screening CT, at this time. The benefit/risk balance for any of the commonly suggested CT screening techniques has yet to be established. These areas need further research. Therefore wild screening should be avoided.

세계적으로 원전의 가동 년수 증가로 인하여 증기발생기와 같은 중요 설비의 교체가 지속적으로 이루어지고 있으며, 해체 시에는 대량의 방사성 금속 폐기물이 일시에 발생한다. 이러한 방사성 폐기물을 규제해제 후에 재활용하기 위해 서는 정확한 잔류방사능을 측정하여야 한다. 그러나, 원자력시설에서 발생되는 금속 폐기물은 형상이 복잡하고, 재질 별 특성이 다양하기 때문에 잔류방사능을 정확히 측정하기가 어렵다. 본 연구에서는 방사성 금속 폐기물의 정확한 잔류방사능을 측정하기 위한 절차를 수립하였고, 오염 대상 선원항 평가, 시료 대표성 확보 방안, 대면적 오염도 측정 장치 제작 및 밀도에 의한 자체흡수 보정인자 등을 평가하였다. 특히, 복잡한 구조의 금속 폐기물에 대하여 시료의 대표성을 확보하기 위하여 용융시킨 후 단순한 형태의 시료를 제조하였으며, 금속의 밀도 차이에 따른 보정인자를 결정하여 방사능 측정 결과의 신뢰성을 향상시켰다.

It has been continuously generated the requirement for the replacement of the main components such as a steam generator due to the deterioration of the nuclear power plant all around the world. Also, a large amount of radioactive metal was generated during the decommissioning in a short period. It is required to make an accurate measurement of the residual radioactivity for recycling the metal waste for releasing from regulatory control. In planning the measurement procedures, the influence of geometry, self-absorption, density and other relevant factors on the representativeness of the measurements should be considered for the decommissioning metal waste. In this study, the method for measurement procedures, the source term evaluation, the ways to secure representative samples, the measurement device for wide area and the self- absorption correction factors for different density were evaluated. The metal samples for measurement were prepared for securing the simple geometry and representative by melting process. The developed correction method for measuring the radioactivity a variety density of metal waste could improve the reliability of the evaluation results for clearance.

비밀봉 방사성물질을 취급하는 시설에서 이들 물질에 의한 작업환경의 다소간의 오염은 피할 수 없다. 오염의 우려가 있는 작업환경에서 오염관리의 일차적인 목적은 방사성물질의 잠재적 체내섭취로 인한 영향이다. 본 논문은 보수적 가정과 간단한 계산에 의거하여 공기오염에 따른 방사성물질의 공기중 농도와 흡입에 의한 연간 섭취량을 산출한 후, 관련 고시에서 정하는 유도공기중농도와 연간섭취한도와 비교함으로써 종사자의 내부피폭 정도를 평가하는 절차를 제공한다. 제시된 절차는 공기중 방사성물질 측정 및 내부피폭 감시의 필요성, 적합한 방호용구의 착용, 배기설비 설계 를 위한 정보 획득 등 공기오염과 종사자의 내부피폭 감시를 위한 실무적 요건을 판단할 목적으로 활용될 수 있다.

Some of radioactive contamination is unavoidable in the facilities using the unsealed radioactive material. The primary purpose of radioactive contamination control in the workplace with contamination concern is the effects from the potential intake of radioactive material into the body. This paper provides procedures to estimate the level of internal exposure for the worker based on the conservative assumptions and simple calculations. They consist of two processes; to calculate air concentration of radioactive material and annual intake by inhalation with contaminated air and to compare each of them to Derived Air Concentration and Annual Limit on Intake mentioned in the related notification. The procedures are applicable to make a decision on practical requirements for monitoring air contamination and internal exposure of worker as follows; needs for measurement of air contamination and internal exposure and acquisition of information on the design of the ventilation system.

국내 가압경수로형 원전 계획예방정비기간에 수행되는 주요 방사선작업에 대한 감마선 에너지 분포를 측정하였다. 고 방사선구역 작업시 종사자가 착용하는 대표적인 납 차폐복에 대하여 감마선 에너지 분포에 따른 차폐효과를 평가하기 위해 전산모사 방법을 이용하였다. 전산모사는 MIRD형 인체모형에 추가적으로 납 차폐복을 모델링하고 측정된 감마 선 에너지 정보를 이용하여 수행하였다. 주요 방사선작업의 평균 감마선 에너지는 일반적으로 방사선방호 과정에서 적용되는 기준 방사선에너지 보다 낮은 것으로 평가되었다. 방사선 방호 목적을 달성하기 위한 효율적인 납 차폐복 착용을 위해 방사선작업 지역의 방사선에너지 분포평가의 필요성을 확인하였다.

The gamma energy distributions at the major working places during refueling outage of Korean PWR nuclear power plants were measured. In order to estimate the dose reduction effect of a lead vest, Monte Carlo calculation method was used. For the simulations, the MIRD-V phantom with a lead vest was formed and exposed to the measured radiation field. The average measured gamma energy is lower than that of standard which is generally applied to radiation protection procedures. For the efficient use of a lead vest and achievement of radiation protection purpose, it is necessary to estimate the energy distribution of radiation field at working places.

원전 방사선작업종사자의 내부선량평가를 위해 일반적으로 사용되고 있는 bed type 전신계측에 몬테카를로 방법을 적용하여 작업자에 대한 외부오염 계측특성을 평가하였다. 한국인 체형을 반영하는 voxel 모의 피폭체를 이용하여 내부오염시 측정 특성을 평가하였다. 외부오염 판별을 위해 BOMAB 모의 피폭체를 이용하여 신체 각 부위별 오염시 나타나는 측정 특성을 평가하였다. 가슴 부위 오염시 누운 자세와 엎드린 자세로 구분하여 외부오염시 계측 특성을 확인하였다. 정량적인 분석을 통해 bed type 전신계측기를 이용한 외부오염 판별이 가능함을 확인하였다.

Monte Carlo method was applied to discriminate the external contamination on radiation workers in nuclear power plants for internal dose assessment generally used with a bed type scanning detector whole body counter. Korean voxel model with internal contamination was used to estimate the detection patterns of whole body scanning. Also, the BOMAB model with various external contamination was assumed to compare with detection of radionuclides inside the human body. From the comparison of detection efficiency between front and back side up, external contamination was easily distinguished.