Earticle

With the reactor operation conditions ‐ 4.3 wt% 235U initial enrichment, burn‐up 55,000 MWd/MTU, average power 34 MW/MTU for three periods burned time for 539.2 days per period and cooling time for 100 hours after shut down, to set up the condition to determine the minimum height (depth) of spent fuel storage pool to shut off the radiation out of the spent fuel storage pool and to store spent fuels safely, the dose rate on the specific position directed to the surface of spent fuel storage pool induced by the neutron and gamma‐ray from spent fuels are evaluated. The length of spent fuel is 381 cm, and as the result of evaluation on each position from the top of spent fuel to the surface of spent fuel storage pool, it is difficult for neutrons from spent fuels to pass through the water layer of maximum 219 cm (600 cm from the floor of spent fuel storage pool) and 419 cm (800 cm from the floor of spent fuel storage pool) for gamma‐ray. Therefore, neutron and gamma‐ray from spent fuels can pass through below 419 cm (800 cm from the floor) water layer directed to the surface of spent fuel storage pool.

To quantitatively evaluate how setup errors in conjunction with dose gradients contribute to the error in IMRT dose quality assurance (DQA) measurements. The control group consisted of 5 DQA plans of which all individual field dose differences were less than ±5%. On the contrary, the examination group was composed of 16 DQA plans where any individual field dose difference was larger than ±10% even though their total dose differences were less than ±5%. The difference in 3D dose gradients between the two groups was estimated in a cube of 6 × 6 × 6 mm3 centered at the verification point. Under the assumption that setup errors existed during the DQA measurements of the examination group, a three dimensional offset point inside the cube was sought out, where the individual field dose difference was minimized. The average dose gradients of the control group along the x, y, and z axes were 0.21, 0.20, and 0.15 cGy․mm-1, respectively, while those of the examination group were 0.64, 0.48, and 0.28 cGy․mm-1, respectively. All 16 plans of the examination group had their own 3D offset points in the cube. The individual field dose differences recalculated at the offset points were mostly diminished and thus the average values of total and individual field dose differences were reduced from 3.1% to 2.2% and 15.4% to 2.2%, respectively. The offset distribution turned out to be random in the 3D coordinate. This study provided the quantitative data that support the large individual field dose difference mainly stems from possible geometric errors (e.g., random setup errors) under the influence of steep dose gradients of IMRT field.

After the first report that electrons with sub-ionization energy of DNA could cause single strand breaks or double strand breaks to DNA, there have been various studies to investigate the mechanisms of DNA damage by low-energy electrons. In this paper, we examined the possibility of using X-ray photoelectron spectroscopy (XPS) to analyze the dissociation patterns of the molecular bonds by electron irradiation on DNA thin films and tried to establish the method as a general tool for studying the radiation damage of biomolecules by low energ yelectrons. For the experiment, pBR322 plasmid DNA solution was formed into the films on tantalum plates by lyophilization and was irradiated by 5-eV electrons. Un-irradiated and irradiated DNA films were compared and analyzed using the XPS technique.

The use of intravenous catheters are occasionally complicated by intravascular fragments and swelling of the catheter fragments. We present a patient in whom an intravenous catheter fragments was retrieved from the dorsal metacarpal vein following its incidental CT examination detection. The case of demonstrates the utility of microscopy and multi‐detector CT in localizing small of subtle intravenous catheter fragments as a human error. A case of IV catheter fragments in the metacarpal vein, in which reproducible and microscopy data allowed complete localization of a missing fragments and guided surgery with respect to the optimal incision site for fragments removal. These reproducible studies may help to determine the best course of action and treatment for the patient who presents with such a case.

Fluence monitor(F/M)는 조사 시편을 원자로의 노심에 넣은 후 방사화 된 조사 시편의 방사능을 측정한 후 역산하여 중성자의 선량을 계산하는 기법으로 원자로내의 중성자 분포를 조사하기 위하여 반드시 필요한 기술이다. 이 기술은 중성자에 대한 에너지 스펙트럼 측정이 간접적으로 가능하며, 현존하는 중성자 분포 측정 기법 중에서 우수한 정밀도를 지니고 있다. 하나로(HANARO)에서 수행하는 재료조사 시험에서의 중성자량 측정을 위하여 본 연구에서는 지름 0.1 mm, 길이 3 mm 미만의 질량 150~200 ㎍ 범위, 순도 99.9% 이상의 Fe, Ni, Ti 와이어를 F/M 시편으로 사용하였다. 이 시편은 알루미늄 캡슐에 봉입하여 30 MW 의 하나로 OR5공에 약 25일간 조사하였다. 조사를 마친 시편은 high purity germanium (HPGe) detector를 이용하여 감마선을 측정하였고, SAND-II code로 reaction rate와 중성자 cross-section등을 고려하여 fluence monitor 위치에서의 중성자 플루언스를 계산하였다. F/M이 장착 되었던 하나로 OR5공의 중성자 플루언스 값은 MCNP 코드를 이용하여 계산된 결과를 사용하였으며, SAND-II code로 장착된 F/M 위치에서의 중성자 플루언스를 계산하여 적용된 시편의 reaction에 따른 결과값의 차이를 비교 분석하였다.

The neutron fluence measurement and evaluation technology is very important for material irradiation test. The most essential technology in this study is the neutron irradiation evaluation method using a fluence monitor. The fluence monitors were fabricated with metal wires of the purity ≥ 99.9%, whose dimensions were 0.1mm diameter, about 3 mm length, and around 150-200 μg mass range. Three wire samples (Fe, Ni, Ti) were prepared for one irradiation aluminum capsule. Five capsules were irradiated in the OR5 hole of the HANARO reactor at 30 MW power for about 25 days. After irradiation tests, radiation activities were measured with the high purity germanium (HPGe) detector. The reaction rates were calculated by using the measured radiation activity data, and then neutron fluence were obtained from the reaction rates and the weighted neutron cross section with calculated neutron spectrum at the fluence monitor position.

우리나라 주요 밭작물(콩, 무, 배추)에 대한 99Tc의 토양-작물체 전이계수(TF)를 조사하기 위하여 온실 내에서 포트실험을 수행하였다. 토양은 경주 방폐장 주변 네 곳(콩 두 곳, 무 및 배추 두 곳)의 밭에서 채취하였다. 파종 3-4 주 전에 건조 토양을 99Tc 용액과 혼합한 다음 포트에 담고 관개하였다. TF 값은 건조 토양 중 99Tc 농도(Bq kg-1-dry)에 대한 작물체 내 농도(Bq kg-1-dry or fresh)의 비로 나타내었다. TF 값은 토양 간에 큰 차이가 없었다. 콩알의 TF 값은 경엽부에 비해 극히 낮아 99Tc의 종실로의 이동성이 매우 낮은 것으로 나타났다. 콩알, 무 뿌리, 무 잎 및 배추 잎에 대한 99Tc 전이계수의 대표치가 각각 두 토양에 대한 산술평균치인 1.8×10-1, 1.2×101, 3.2×102, 1.3×102(건조 작물체 기준)로 제안되었다. 채소류의 경우 신선 작물체에 대한 대표치도 제안되었다. 본 제안치는 대표성이 충분치 못하므로 지속적으로 최신화 할 필요가 있다.

In order to investigate the soil-to-plant transfer factor (TF) of 99Tc for Korean major upland crops (soybean, radish and Chinese cabbage), pot experiments were performed in a greenhouse. Soils were collected from four upland fields (two for soybean and two for radish and Chinese cabbage) around Gyeongju radioactive-waste disposal site. Three to four weeks before sowing, dried soils were mixed with a 99Tc solution and the mixtures were put into pots and irrigated. TF values were expressed as the ratios of the 99Tc concentrations in plants (Bq kg-1-dry or fresh) to those in soils (Bq kg-1-dry). There was no great difference in the TF value between soils. The TF values for soybean seeds were extremely lower than those for the straws, indicating a very low mobility of 99Tc to seeds. As representative TF values of 99Tc, 1.8×10-1, 1.2×101, 3.2×102 and 1.3×102 (for dry plants), arithmetic means for two soils, were proposed for soybean seeds, radish roots, radish leaves and Chinese cabbage leaves, respectively. In the case of the vegetables, proposals for fresh plants were also made. The proposed values are not sufficiently representative so successive updates are needed.

CR(computed radiography)시스템의 영상획득 과정에서 영상판의 외부 방사선 영향을 효과적으로 보완하고 임상적용시 효율적 활용을 목적으로 본 연구를 실시하였다. 이를 위하여 영상판의 보관 장소와 기간으로 분류하여 미소한 흑점 차이를 비교 분석하고 영상의 경계면에서 농도 분포를 평가하였다. 영상판의 보관 장소에 따른 명실과 암실에서 흑점 수를 비교 측정한 결과, 명실에 보관한 영상판에서 1일과 2일에서 미약하게 흑점 수가 증가하였으며, 4일, 6일, 8일, 10일로 보관 기간이 길어질수록 비례하여 증가하였다. 하지만 암실 보관의 경우 명실과 비교시 흑점 수가 현저하게 줄어들었다. 영상판의 위치에 따른 화질의 변화에서는 가장자리 보다 중앙에 관심영역을 위치시키는 것이 화질의 손상을 줄일 수 있었다. 피사체의 두께 변화에 따른 선예도 차이는 가능한 피사체 두께를 작게 하는 것이 산란선 발생을 줄이고 선예도를 향상시키는 것으로 나타났다. 따라서 우수한 화질의 의료영상을 얻기 위해서는 영상판의 효율적 정도관리가 필요하며 영상판을 암박스에 보관하여 외부 방사선에 장시간 방치하지 않도록 하는 것이 바람직하다.

Lab effectively supplemented the effects of outside radiation on image plates in the process of image acquisition of CR (computed radiography) systems and conducted for effective utilization in the case of clinical application. For this, Lab classified the storage places and time periods of image plates and compared and analyzed the differences between small dark spots. Lab also assessed the concentration distribution within the boundaries of images. Lab compared and measured the number of dark spots in a light room and a dark room depending on the storage places of image plates and found that dark spots slightly increased in an image plate when stored in a light room on the first and second days. Dark spots increased in proportion to the length of time stored. In the case of the image plate stored in a dark room, the number of dark spots remarkably decreased. With regard to picture quality as related to the location of image plates, the damage to picture quality could be reduced by locating regions of interest in the center. With regard to differences in sharpness following changes in the thickness of subjects, fewer scatter rays occurred and sharpness improved by reducing the thickness of subjects as much as possible. To get medical images of excellent quality, image plates should be managed effectively and it is desirable to keep images plates in dark iron plate boxes and not to expose them to outside radiation for a long time.

일반적으로 사용되는 액체섬광계수기를 이용한 226Ra 분석에는 Ba 공침법을 통해 얻어진 Ba(Ra)SO4 침전물을 이용하게 된다. 그러나, 인산석고 침출수의 경우 SO42-, Ca2+등의 이온이 다량 존재하여 순수한 Ba(Ra)SO4 침전물을 얻기가 힘들기 때문에 정확한 분석이 매우 어렵다. 본 연구에서는 분석화학에서 금속이온의 분리에 일반적으로 많이 활용되는 Ethylenediaminetetraacetic acid (EDTA)를 이용하여 인산석고 침출수에서의 Ba 공침법을 개발하였고 실제 인산석고 야적장 주변 침출수의 분석에 적용하였다. 또한 개발된 분석 방법은 침출수와 유사한 매질의 226Ra 모의표준시료을 제조하여 확인하였고 IAEA-434 인증표준물질을 통해 분석 신뢰성을 검증하였다. 실제 인산석고 야적장 침출수를 분석한 결과 0.102 Bq·kg-1의 농도를 보였고 검출하한치는 3.4 mBq·kg-1였다. 226Ra 모의표준시료 분석을 통한 측정농도는 첨가한 농도와 1% 내외로 잘 일치하며 좋은 상관관계(R2=0.99)를 보였다. 인증표준물질의 분석 결과 인증값과 비교하여 5.8% (k=1)이내로 잘 일치하였다.

Ba is the most useful element to get the Ba(Ra)SO4 precipitate. However, when the high concentrations of ions such as sulfate, calcium are existed in the leachate of phosphogypsum stack, it is difficult to get the Ba(Ra)SO4 precipitate. Since this reason, the developed method for the Ba coprecipitate using EDTA was performed to determine the 226Ra concentration in the high sulfate sample. The average concentration of 226Ra in a leachate of phosphogypsum using this method was 0.102 Bq·kg-1 and the minimal detectable activity is 3.4 mBq·kg-1. The 226Ra stock solution and the CRM (Certified Reference Material) were analyzed to verify this method. In analyzed 226Ra stock solution, bias with added concentration was approximately 1% and the correlation curve between 226Ra concentration in simulated standard sample and measured 226Ra concentration showed good agreement with a correlation coefficient (R2) of 0.99. In analyzed CRM, maximum bias with reference value was 5.8% (k=1) and the analytical results were in good agreement with the reference value.

방사선이용의 사회적 수용성 제고 방안의 일환으로 일반대중 가운데 장기적인 관점에서 여론의 주도층 역할을 하게 될 대학생을 대상으로 전공자와 비전공자 사이에 방사선이용 분야별 필요성 인식 차이를 파악하여 방사선이용에 대한 국민이해 증진사업의 효율적인 전략구상에 필요한 근거자료를 제공하고자 한다. 2010년 11월 교육통계서비스(http://cesi.kedi.re.kr) 기준, 전국 4년제 대학교 177개교, 전문대학 146개교 중 전체 24.0%에 해당하는 78개교의 재학생을 표본으로 선정하여 방사선이용 분야별 필요성 인식수준을 설문조사 하였다. 그 결과 전공자와 비전공자 모두 의료분야의 필요성 인식수준이 높았고, 전공자와 비전공자 모두 농업분야의 필요성 인식수준이 가장 낮게 나타났다. 6개 방사선이용 분야 모두 전공자가 비전공자보다 필요성 인식수준을 높게 나타냈다. 각 분야별로 남학생, 의료방사선 경험이 있는 경우, 관련 교육을 받은 경우에 필요성 인식수준이 높았다. 이는 여학생, 의료방사선 경험이 없는 경우, 관련 교육경험이 없는 경우에 대해서는 보다 다양한 정보제공으로 필요성 인식 수준을 상대적으로 더 높일 필요가 있다고 본다. 각 지역별, 방사선이용 분야별 정책결정에 있어서 본 연구결과에 나타난 집단의 특성을 고려한다면 방사선이용에 대한 국민이해 증진사업을 효율적으로 달성하는데 도움이 될 것이라고 사료된다.

s a way of improving social receptivity of using radiation, this study looked into the difference of understanding the need of using radiation in various fields between students majoring in radiation and non-radiation related studies, who will influence public opinion in the long term. This study also provides data needed for developing efficient strategies for projects promoting the public’s awareness of using radiation. Of the students in the 79 schools sampled, 24%(177) were in 4 year colleges and 146 were junior colleges in educational statistics service (http://cesi.kedi.re.kr) In November 2010 1,945 students were selected as a sample, and they were given surveys on the need of using radiation in different fields. As a result, both between students majoring in radiation and non-radiation related studies showed a high level of understanding the need for radiation in the medical field and showed a low level of understanding of the need for radiation in the agricultural field. In all 6 fields of radiation use, students majoring in radiation related studies showed higher levels of understanding for the need to use radiation than students majoring in radiation and non-radiation related studies. In each field, male students and those who have experience medical radiation and relevant education had higher level of understanding. This shows we need to improve the understanding of the cases of female students and those who have not had experiences with medical radiation and to provide relevant education through various kinds of information. The characteristics of the groups that are shown in the results of this study are considered to be helpful for efficiently for project promoting the public’s awareness of using radiation.