Earticle

To determine the biological effects of low‐dose‐rate radiation (137Cs, 2.95 mGy/h) on EL4 lymphoma cells during 24 h, we investigated the expression of genes related to apoptosis, cell cycle arrest, DNA repair, iron transport, and ribonucleotide reductase. EL4 cells were continuously exposed to low‐dose‐rate radiation (total dose: 70.8 mGy) for 24 h. We analyzed cell proliferation and apoptosis by trypan blue exclusion and flow cytometry, gene expression by real‐time PCR, and protein levels with the apoptosis ELISA kit. Apoptosis increased in the low‐dose‐rate irradiated cells, but cell number did not differ between non‐ (Non‐IR) and low‐dose‐rate irradiated (LDR‐IR) cells. In concordance with apoptotic rate, the transcriptional activity of ATM, p53, p21, and Parp was upregulated in the LDR‐IR cells. Similarly, Phospho‐p53 (Ser15), cleaved caspase 3 (Asp175), and cleaved Parp (Asp214) expression was upregulated in the LDR‐IR cells. No difference was observed in the mRNA expression of DNA repair‐related genes (Msh2, Msh3, Wrn, Lig4, Neil3, ERCC8, and ERCC6) between Non‐IR and LDR‐IR cells. Interestingly, the mRNA of Trfc was upregulated in the LDR‐IR cells. Therefore, we suggest that short‐term low‐dose‐rate radiation activates apoptosis in EL4 lymphoma cells.

The second phase of the national program for fusion energy development in Korea starts from 2012 for design and construction of the fusion DEMO reactor. Radiological assessment for the fusion reactor is one of the key tasks to assure its licensability and the starting point of the assessment is determination of the source terms. As the first effort, the activities of the coolant due to activated corrosion product (ACP) were estimated. Data and experiences from fission reactors were used, in part, in the calculations of the ACP concentrations because of lack of operating experience for fusion reactors. The MCNPX code was used to determine neutron spectra and intensities at the coolant locations and the FISPACT code was used to estimate the ACP activities in the coolant of the fusion DEMO reactor. The calculated specific activities of the most nuclides in the fusion DEMO reactor coolant were 2‐15 times lower than those in the PWR coolant, but the specific activities of 57Co and 57Ni were expected to be much higher than in the PWR coolant. The preliminary results of this study can be used to figure out the approximate radiological conditions and to establish a tentative set of radiological design criteria for the systems carrying coolant in the design phase of the fusion DEMO reactor.

Silicon carbide (SiC) is a promising material for neutron detection at harsh environments because of its capability to withstand strong radiation fields and high temperatures. Two PIN-type SiC semiconductor neutron detectors, which can be used for nuclear power plant (NPP) applications, such as in-core reactor neutron flux monitoring and measurement, were designed and fabricated. As a preliminary test, MCNPX simulations were performed to estimate reaction probabilities with respect to neutron energies. In the experiment, I-V curves were measured to confirm the diode characteristic of the detectors, and pulse height spectra were measured for neutron responses by using a 252Cf neutron source at KRISS (Korea Research Institute of Standards and Science), and a Tandem accelerator at KIGAM (Korea Institute of Geoscience and Mineral Resources). The neutron counts of the detector were linearly increased as the incident neutron flux got larger.

2011년 3월 11일 일본 후쿠시마(福島) 원전 사고 1주년을 계기로 청소년의 방사선 인식도를 알아 본 뒤 이를 일반 성인을 대상으로 동일 설문을 이용해 거의 비슷한 시기에 조사한 결과와 비교하고자 하였다. 연구 방법론적 설계는 양적 조사를 하고, 빈도 분석을 하였다. 조사 대상은 미래 세대인 15세 중학교 3학년 학생으로 한정하였으며, 조사 도구인 설문지를 직접 배포하여 유효 응답지인 2,217부를 기준으로 분석하였다. 설문은 40문항으로 구성하였으며, 하 위 영역별 크론바하 알파(Cronbach's ) 계수는 ‘방사선의 자아 인식’ 0.494, ‘방사선의 위험’ 0.843, ‘방사선의 편익’ 0.748, ‘방사선의 안전관리’ 0.692, ‘방사선의 정보원’ 0.819, ‘후쿠시마 사고의 영향 정도’ 0.675로 대부분 높은 것으로 나타났다. 설문 분석 결과 응답자의 방사선 개념에 대한 지식은 100점 만점으로 환산시 67.4점(성인 69.5점)으로 높지 않았다. 후쿠시마 사고의 영향은 성인보다 덜 받은 것으로 조사됐는데, 다음 문항에서 ‘그렇다’ 또는 ‘매우 그렇다’고 응답한 비율에서 잘 드러난다. ‘후쿠시마 사고의 영향으로 원전을 하지 말아야 한다는 쪽으로 생각을 바꿨다’는 문항에는 전체의 27.0%(성인은 38.9%)가, ‘후쿠시마 원전 사고로 인한 피해는 측정이 불가능할 만큼 막대하다’는 문항에는 전체의 65.7%(성인은 86.6%)가, ‘후쿠시마 원전 사고는 원자력 발전소 안전에 대한 경각심을 높이는 데 기여하였다’는 문항에는 전체의 65.0%(성인 86.3%)가 그 같이 응답해 청소년의 후쿠시마 사고의 영향 정도가 상대적으로 낮은 것을 알 수 있다. 또 상당수의 문항에서 청소년들은 성인에 비해 ‘보통이다’라고 응답하는 비율이 높았는데, 이는 아직 청소년 자신의 방사선에 대한 인식이 제대로 정립되지 않았기 때문으로 해석된다. 본 연구는 후쿠시마 원전 사고 이후 국내에서 청소년을 대상으로 방사선 인식도를 처음 조사했고, 일반 성인 조사 결과와도 비교한 것으로, 향후 정부의 방사선 정책 수립에 크게 기여할 것으로 기대된다.

Marking the first anniversary of the Fukushima nuclear accident, which took place on March 11th, 2011, the level of adolescent awareness and understanding of radiation was surveyed, and the results were then compared with those for adults with the same questionnaires conducted at similar times. A qualitative survey and frequency analysis were made for the design of the study methodology. Those surveyed were limited to 3rd grade middle school students, 15 years of age, who are the future generation. The questionnaire, which is a survey tool, was directly distributed to the students and 2,217 answers were analysed. The questionnaires were composed of 40 questions, and it was found that Cronbach's coefficient was high with 'self awareness of radiation' at 0.494, 'risk of radiation' at 0.843, 'benefit of radiation' at 0.748, 'radiological safety control' at 0.692, 'information sources of radiation' at 0.819, and 'impacts of Fukushima accident'. The results of the survey analysis showed that the students' knowledge of radiation was not very high with 67.4 points (69.5 points for adults) calculated on a maximum scale of 100 points (converted points). The impacts of the Fukushima nuclear accident were found to be less significant to adolescents than adults, and the rate of answer of "so" or " very so" in the following questions demonstrates this well. It was also shown that the impacts of the Fukushima accident to adolescents were comparatively low with 27.0% (38.9% for adults) on the question of "attitude changed against nuclear power due to the Fukushima accident," 65.7%( 86.6% for adults) on the question of "the damages from the Fukushima accident was immeasurably huge," and 65.0% (86.3% for adults) on "the Fukushima accident contributed to raising awareness on the safety of nuclear power plants". The adolescents had a high rate of "average" answers on most of the questions compared with adults, and it can be construed that this resulted from adolescent awareness of radiation not being firmly rooted on themselves. This study was the first of its kind for surveying adolescents regarding the level of awareness of radiation after the Fukushima accident, and the results were compared with the survey results of adults, and they are expected to greatly contribute toward establishing a radiation policy by the government in the future.

임상에서 사용하고 있는 흉부 CT촬영의 저선량 프로토콜과 표준선량 프로토콜 간의 선량과 화질을 비교 분석하였다. 흉부 저선량 프로토콜(120 kVp, 30 mAs)과 표준선량 프로토콜(120 kVp, 180 mAs)로 촬영(BrillianceTM CT 16slice, PHILIPS)한 61명의 조영제를 사용하지 않은 영상에서 기관 분기부 위치의 종격동 영상을 본 연구를 위해 사용하였다. 행대동맥과 가시아래근에서 CT number와 잡음을 측정하였고, Back-ground 잡음을 측정하여 신호대잡음비 (signal-to-noise ratio. SNR)와 대조도잡음비(contrast-to-noise ratio, CNR)를 구하였다. 두부 아크릴 팬텀을 이용하여 선량을 측정하였고, 워터 팬텀으로 얻은 영상에서 CT number와 잡음을 측정하였다. 모든 측정은 3회 실시하여 평균값 을 SPSS 프로그램(version 14.0)으로 분석하였고, 그래프는 시그마 플롯 프로그램(version10.0)을 사용하였다. 결과: 상행대동맥과 가시아래근에서 저선량 프로토콜 영상이 표준선량 프로토콜 영상 보다 유의하게 높은 잡음을 보였 고, SNR과 CNR은 유의하게 낮았다. 두 영상에서 비만지수에 대한 잡음은 양의 관련성을 보였지만, SNR과 CNR은 음의 관련성을 보였다. 팬텀 결과에서 저선량 프로토콜의 선량이 표준선량 프로토콜 보다 유의하게 낮았지만(0.35 mGy vs. 1.95 mGy, p=0.008), 잡음은 저선량 프로토콜에서 유의하게 높았다(p=0.029). 저선량 프로토콜이 표준선량 프로토콜 보다 유의하게 낮은 선량을 보였지만, 화질 평가도 유의하게 낮은 결과를 보임으로서 임상에서 사용하는 저선량 프로토콜의 노출 선량은 화질을 고려하여 상향 조정할 필요가 있다.

The purpose of this study was to compare radiation dose and image quality between low-dose (LDP) and standard-dose protocol (SDP). LDP (120 kVp, 30 mAs, 2-mm thickness) and SDP (120 kVp, 180 mAs, 1.2-mm thickness) images obtained from 61 subjects were retrospectively evaluated at level of carina bifurcation, using multi-detector CT (Brilliance 16, Philips Medical Systems). Signal-to-noise ratio (SNR) and contrast-to-noise ratio (CNR) were calculated at ascending aorta and infraspinatus muscle, from CT number and back-ground noise. Radiation dose from two protocols measured at 5-point using acrylic-phantom, and CT number and noise measured at 4-point using water-phantom. All statistical analysis were performed using SPSS 19.0 program. LDP images showed significantly more noise and a significantly lower SNR and CNR than did SDP images at ascending aorta and infraspinatus muscle. Noise, SNR and CNR were significantly correlated with body mass index (p＜0.001). Radiation dose, SNR and CNR from phantom were significant differences between two protocols. LDP showed a significant reduction of radiation dose with a significant change in SNR and CNR compared with SDP. Therefore, exposure dose on LDP in clinical applications needs resetting highly more considering image quality.

Radiocaesium과 radiostrontium에 대한 벼의 흡수억제 대책으로서 K와 Ca의 동시처리 효과를 조사하기 위하여 온실 내에서 방사성 추적자 실험을 수행하였다. 흙상자에 담긴 논토양(pH 6.5의 양토)에 137Cs와 85Sr을 가하고 농업용 KCl과 Ca(OH)2를 사용하여 K와 Ca를 처리한 다음 모내기하였다. 대조 작물체의 쌀알에 대한 137Cs와 85Sr의 토양-작물체 전이계수(TF, m2 kg-1-dry)는 각각 7.4×10-5 및 2.1×10-4였고 볏짚의 경우에는 각각 2.6×10-4 및 2.2×10-2였다. K와 Ca의 동시처리 수준(K/Ca, g m-2)이 137Cs의 경우 33.6/322까지, 85Sr의 경우 48.0/460까지 증가할수록 전이계수가 점점 감소하였다. 최고 감소율은 두 핵종 모두 60% 정도였다. 85Sr 전이계수는 33.6/322 처리에서도 60% 가까이 감소하였다. 당 처리에서는 벼의 생산성도 양호하였다. 이로써 본 실험에서는 33.6/322 처리가 최적인 것으로 판단되었다. 최적처리 수준은 각종 요인에 따라 다를 수 있으므로 차후 다양한 조건에 대한 실험이 수행될 필요가 있다.

A radio-tracer experiment was performed in a greenhouse to investigate the effectiveness of the simultaneous application of K and Ca as a countermeasure for reducing the radiocaesium and radiostrontium uptake by rice. Paddy soil (loam of pH 6.5) in soil boxes was spiked with 137Cs and 85Sr, and treated with K and Ca in the forms of KCl and Ca(OH)2, respectively, at agrochemical grades before transplanting. For the seeds of the control plants, soil-to-plant transfer factors (TF, m2 kg-1-dry) of 137Cs and 85Sr were 7.4×10-5 and 2.1×10-4, respectively, whereas the corresponding values for the straws were 2.6×10-4 and 2.2×10-2, respectively. The TF values of 137Cs and 85Sr kept decreasing as the level of the simultaneous application of K and Ca (K/Ca, g m-2) increased up to 33.6/322 and 48.0/460, respectively. The maximum rate of the decrease was around 60% for both radionuclides. Nearly 60% reduction in the TF value of 85Sr was observed even at the dosage of 33.6/322, which was considered the optimum dosage based on crop productivity as well as reduction in the radiocaesium and radiostrontium uptake by rice. The optimum dosage may depend on various factors so further experiments need to be made for many different conditions.

2011년 국제방사선방호위원회(ICRP)는 최근 역학 조사들을 근거로 방사선영향으로 발생할 수 있는 암 외 질환의 위험에 대한 권고를 개정하였다. 특히 수정체 조직반응의 발단선량을 0.5 Gy로 하향 조정하면서, 계획 피폭상황에서 직무피폭 시 수정체 등가선량한도를 “정해진 5년 기간 동안 평균해서 연간 20 mSv, 그 중 어느 한 해에도 50 mSv를 초과하지 않아야 한다”로 권고하였다. 방사선작업종사자의 외부선량은 개인 열형광선량계(TLD)를 사용하여 감시하고 있으며 판독한 열형광소자별 반응도를 선량평가 알고리즘에 적용하면 개인의 수정체 등가선량을 구할 수 있다. 본 논문에서는 성능검사에 사용된 Harshaw TLD의 소자반응도를 사용하여 현재 사용 중인 알고리즘들에 의한 수정체 등가선량을 평가하였다. 그 결과 성능검사에 사용된 TLD의 소자반응도를 사용하여 수정체 등가선량을 평가한 경우 알고리즘 간의 상대오차는 최대 48.84% 내에 있는 것으로 나타났다.

International Commission on Radiological Protection (ICRP) has revised its recommendations concerning the tissue reaction to ionizing radiation in accordance with consideration of the detriment arising from non-cancer effects of radiation on health based on recent epidemiological basis. Particularly, for the lens of the eye, the threshold in absorbed dose revised to be 0.5 Gy, for occupational exposure in planned exposure situation the commission recommended "An equivalent dose limit for the lens of the eye of 20 mSv in a year, averaged over defined periods of 5 years, with no single year exceeding 50 mSv." To monitor the radiation exposure of radiation worker, TLD is typically provided and the lens of eye dose can be assessed by run of dose calculation algorithm with TL element response data. This study is to assess equivalent dose of the lens of eye using the Harshaw TLD system and its two different dose calculation algorithms. The result provides the Harshaw TLD system showed the assessment of the lens of eye dose with 48.84% error range.

PET-CT 검사 환자의 피폭선량 감소를 위한 기초자료 제공의 일환으로 PET-CT 검사 환자의 방사선량률의 변화를 분석 하고자 하였다. PET-CT 검사 환자의 방사선량률을 측정한 결과 이론과 같이 방사성의약품이 투여된 환자로부터 거리가 멀수록, 시간이 지날수록 방사선량률은 감소되는 것을 볼 수 있었다. 특히 신체부위에 따라서는 방사성의약품 정맥주사 즉시인 약 4.17분에서는 흉부, PET-CT 검사 전 배뇨 후인 약 77.47분 이후부터는 두부가 가장 높게 나타났다. 일반화되어 있는 정보와 같이 PET-CT 검사 환자로부터 받는 방사선 피폭량을 감소시키기 위해서는 보호자나 방사선작업종사자가 환자로부터 거리를 멀리하거나 방사능이 감소된 이후의 시간부터 접촉하는 것이 바람직하다. 불가피한 접촉이 필요하다면 가능한 거리는 200 cm이상을 확보하는 것이 바람직하다. 또한 초기에는 흉부, 방사성의약품 투여 후 약 77분 이후부터는 두부에 방사선량률이 높기 때문에 환자 신체적 특징을 고려한 접촉도 함께 이루어진다면 최적화 달성에 도움이 될 것이라고 보여 진다. 본 연구에서 도출된 PET-CT 검사 환자의 거리, 시간, 신체부위에 따른 방사 선량률 변화를 알 수 있다는 점에서 연구에 의의가 있다고 본다. 향후 연구에서는 본 연구에서 도출된 결과를 바탕으로 환자 개인특성에 따른 방사선량률의 변화 차이를 분석하여 환자, 보호자, 종사자의 피폭선량 감소에 활용할 수 있도 록 지속적인 연구가 수행되는 것이 필요하다고 본다.

This paper analyzes changes in the external radiation dose rate of PET-CT test patients as a part of providing basic materials for reduction of radiation exposure to PET-CT test patients. In theory the measurement of external radiation dose rate of PET-CT test patients shows that the further the distance from the patient injected with radioactive pharmaceutical and a longer time elapsement from the injection leads to a smaller amount of radiation. Particularly, the amount of radiation marked the highest in the chest was at 4.17 minutes immediately after the intravenous injection and in the head after 77.47 minutes after urination in advance to the PET-CT test. As in the generalized information, it is desired to keep distance between the patient and caretakers or professionals to reduce the amount of radiation exposure from PET-CT test patients and to resume contact the patient after the time when the radiation has reduced. If contact is unavoidable, it is desired to keep at least 200cm from the patient. In addition, the amount of radiation reached the highest in the chest at first and then in the head from 77 minutes after injection. Accordingly, it would be helpful in achieving the optimization if contact is made based on the patient's physical characteristics. This study is significant as it measures changes in radiation the dose rate by; distance from the PET-CT test patient, time elapsed, and specific parts of body. Further studies based on the findings in this paper are required to analyze changes in radiation dose rate in accordance with individual characteristics unique to PET-CT patients and to utilize the results to reduce the amount of radiation patient, caretakers and professions are exposed.