• Title/Summary/Keyword: 갑상선방호

Search Result 13, Processing Time 0.023 seconds

인터뷰 - 세계원자력협회(WNA) Agneta Rising 사무총장

  • Kim, So-Yeon
    • Nuclear industry
    • /
    • v.35 no.9
    • /
    • pp.46-52
    • /
    • 2015
  • 1975년 우라늄협회로 출발한 세계원자력협회(WNA)는 원자력을 평화적으로 이용하는 것을 적극 지원하고, 원자력 발전과 핵연료주기 전반에 걸친 원자력 산업 발전을 위하고자 설립한 세계적 민간 기구로, 우라늄 채광부터 변환, 농축, 핵연료 제조, 원자력발전 운영, 기자재(설비) 제작 및 사용후핵연료 처분에 이르기까지 원자력발전의 전 주기 산업을 촉진하고 관련 정보를 지원하고 있다. 2001년 지금의 명칭으로 변경한 WNA는 전 세계 원자력산업체와 원자력 관련 기관, 대학 등 175개 회원사를 두고 상호 협력과 전문 인력 교육 기반 강화, 국제화에 적극 나서고 있으며, 원자력산업 정보 제공과 교환을 위해 관련 보고서와 자료도 수시로 발행하고 있다. 2013년부터 WNA를 이끌고 있는 아그네타 라이징 사무총장은 지난 11월 영국 런던 소재 WNA를 방문한 <원자력신문>과의 인터뷰를 통해, 원전과 주변지역 주민의 갑상선암 발병에 대한 인과 관계에 대하여 "갑상선암 발병이 원전과 연관성 있다는 주장은 과학적 근거가 없다"고 단호히 말하고, "한국과 유사한 사례가 해외 원자력계(과학계)와 의학계에 보고된 적이 있냐"는 질문에 "해외에서 정상 운영되고 있는 원전 시설은 국제방사선방호위원회(ICRP)의 엄격한 기준(ICRP-60)이 적용하고 있으며, 방사선 방호와 관련된 연구보고서(논문)를 꾸준히 내고 있지만 원전 주변 주민에 대한 여러 역학 조사에서도 갑상선암이 증가했다는 사례는 보고된 바 없다"고 말했다. 또한 "실제로 일본 원폭 생존자 연구와 체르노빌 원전 주변 주민 연구에 의하면 20세 이상의 성인에서 방사선 노출에 의해 갑상선암이 증가한다는 증거는 없었다."면서 "체르노빌 사고와 후쿠시마 원전 사고 이후 방사선 누출로 인해 방사선이 갑상선암의 발생률을 증가시키는 것으로 알려졌지만 실제로 원전에서 발생하는 방사능은 갑상선암을 유발시킬 수 있는 양에 비해 아주 적다. 그럼에도 원전 시설에서 나오는 방사능 수치에 대해 제대로 밝히는 기관이 없기 때문에 원전 주변에 살아도 영향을 받는 것으로 오해할 수 있다."고 덧붙였다. 아그네타 라이징 사무총장은 스웨덴 출신의 방사선 방호 전문가로, 스웨덴 국영기업 Vattenfall AB 그룹에서 원자력 에너지 환경 분야 최고 전문가로 활동했으며, 스웨덴원자력학회, 유럽원자력학회, 세계여성원자력전문인회(WiN-Global) 회장 등을 역임했다. 인터뷰 전문을 게재한다.

  • PDF

Analysis of the Effectiveness of Emergency Response Measures during the Design Basis Accident of the Research Reactor 'HANARO' using MACCS2 Code (MACCS2 코드를 이용한 연구용원자로 '하나로' 설계기준사고시 비상대응조치 효과분석)

  • Lee, Goan-Yup;Kim, Jong-Su;Lee, Hae-Cho;Kim, Bong-Suk
    • Journal of Radiation Protection and Research
    • /
    • v.39 no.2
    • /
    • pp.109-117
    • /
    • 2014
  • Nuclear emergency planning is to plan sheltering, evacuation and iodine prophylaxis for the residents living in the area where the emergency plan is needed, the area is confirmed based on the dose assessment using the source-term through an accident analysis and the data measured from meteorological tower. In this study, the does change before and after protective measures was assessed stochastically based on the one year meteorological data in the condition of the maximum hypothetical accident which can be considered at the research reactor 'HANARO', and the optimized protective measures were derived based on the reference levels defined as a residual dose by ICRP 2007 recommendation which can be applied in a emergency exposure situation. The optimized protective measures for the HANARO in the maximum hypothetical accident were the evacuation to radius 300 m, the sheltering from 300 m to 800 m, the iodine prophylaxis only for the emergency workers under the protective measures for non emergency workers.

Assessment of Occupational Dose to the Staff of Interventional Radiology Using Monte Carlo Simulations (몬테카를로 방법을 이용한 중재방사선시술자에 대한 선량평가)

  • Lim, Young-Khi
    • Journal of Radiation Protection and Research
    • /
    • v.39 no.4
    • /
    • pp.213-217
    • /
    • 2014
  • Medical operations and diagnosis using interventional radiology techniques have been increased. The management and monitoring of occupational radiation exposure to the staff of interventional radiology become important, specially because they stand in close proximity to the patient. The operational radiation protection quantity, Hp(10) which can be obtained from personal dosimeter do not always represent the effective dose to the staff. So, in this study, to estimate the critical organ doses to the staff of interventional radiology, Monte Carlo calculations with mathematical human phantom and dose measurements with personal dosimeters were carried out for the major interventional radiology procedures using C-arm. Results showed that the values of Hp(10) measured by personal dosimeters were higher than critical organ doses which were calculated. And the calculated dose to thyroids was much higher than those of other critical organ doses. For the proper radiation protection of the medical staff of interventional radiology, additional radiation protection for thyroids as well as for whole body shielding like wearing a lead apron should be considered.

Invivo Dosimetry for Mammography with and without Lead Apron Using the Glass Dosimeters (유방촬영술에서 유리선량계를 이용한 납치마의 선량차폐 효과 측정)

  • Yu, Su-Jeong;Lim, Sangwook;Ma, Sun Young;Seo, Sun-Youl;Kim, Young-Jae;Kang, Young-Nam;Keum, Ki Chang;Cho, Samju
    • Progress in Medical Physics
    • /
    • v.26 no.2
    • /
    • pp.93-98
    • /
    • 2015
  • The purpose of this study is to see the usefulness of lead apron for critical organs near the breast under examining. For clinical experiment, 30 female volunteers who agreed to their participation in the experiments, were chosen and divided into two groups, 15 in group A and 15 in group B respectively. group A is to see whether each side of breast under mammography affects to other side glandular on the critical organs is same, because it is not allowed to scan the both breast for same person or to scan repeatedly. Group B is to see the effectiveness of lead apron during the mammography of right breast. Glass dosimeters were placed on the thyroid, the contralateral breast, and lower abdomen where near the breast during examining. The average glandular doses on the surface in mammography of the thyroid gland, the contralateral breast, the lower abdomen were 0.0692 mGy, 0.6790 mGy, and 0.0122 mGy, respectively, which was an extremely low level of glandular dose. In group B, as to the thyroid gland, average dose was decreased from 0.0922 mGy to 0.0158 mGy. The average dose of contralateral breast was decreased from 0.8575 mGy to 0.0286 mGy. The average doses of lower abdomen was decrease 0.0150 mGy to 0.0173 mGy. As to the lower abdomen, dose decreased from 0.0150 mGy before the use of an apron down to 0.0173 mGy after the use. As p-value was under 0.05, statistically significant difference was observed between the two groups. Wearing an apron can have the protective effects on the thyroid gland up to 20 times lower than not wearing one. Besides, it is also necessary to protect the other breast during the examination by wearing one.

Effect of Selenium on the Thyroid gland Antioxidative Metabolisms in Rat Model by Ionizing Radiation (셀레늄이 전리방사선에 의한 힌쥐 모델에서의 갑상선 항산화계에 미치는 영향)

  • Choi, Hyung-Seok;Choi, Jun-Hyeok;Jung, Do-Young;Kim, Jang-Oh;Shin, Ji-Hye;Min, Byung-In
    • Journal of radiological science and technology
    • /
    • v.40 no.1
    • /
    • pp.135-142
    • /
    • 2017
  • Selenium (Se), which is natural materials existing was known as an important component of selenoprotein, one of the important proteins responsible for the redox pump of a living body. Selenium was orally administered to Rat and irradiated with 10 Gy of radiation. Then, the thyroid gland was used as a target organ for 1 day, 7 days and 21 days to investigate the radiation protection effect of selenium (Se) through changes of blood components, thyroid hormones (T3, T4), antioxidant enzyme (GPx) activity and thyroid tissue changes. As a result, there was a significant protective effect of hematopoietic immune system(hemoglobin concentration, neutrophil, platelet)(p<0.05). The activity of Glutathione Peroxidase (GPx), the antioxidant enzyme, and the activity of the target organ, thyroid hormone (T3, T4), also showed significant activity changes (p<0.05). In the observation of tissue changes, it was confirmed that there was a protective effect of thyroid cell damage which caused the cell necrosis by radiation treatment. Therefore, it is considered that selenium(Se) can be utilized as a radiation defense agent by inducing immunogenic activity effect of a living body.

A Study on the Effect of Containment Filtered Venting System to Off-site under Severe Accident (중대사고시 격납건물여과배기계통(CFVS)적용으로 인한 사고영향과 결과 고찰)

  • Jeon, Ju Young;Kwon, Tae-Eun;Lee, Jai-Ki
    • Journal of Radiation Protection and Research
    • /
    • v.40 no.4
    • /
    • pp.244-251
    • /
    • 2015
  • The containment filtered venting system reduces the range of the contamination area around the nuclear power plant by strengthening the integrity of the containment building. In this study, the probabilistic assessment code MACCS2 was used to assess the effect of the CFVS to off-site. The accident source term was selected from a Probabilistic Safety Analysis report of SHINKORI 1&2 Nuclear Power Plant. The three source term categories from 19 STC were chosen to evaluate the effective dose and thyroid dose of residents around the power plant and the dose with CFVS and without CFVS were compared. The dose was calculated according to the distance from the nuclear power plant, so the damage scale based on the distance that exceeds the IAEA criteria for effective dose (100 mSv per 7 days) and thyroid dose (50 mSv per 7 days) were compared. The effective dose reduction rates of the STC-3, STC-4, STC-6 were about 95-99% in the whole range (0~35 km), 96-98% for the thyroid dose. There are similar results between effective dose and thyroid dose. After applying the CFVS, the damage scale that exceeds the effective dose criteria was about 1 km (mean). Especially, the STC-4 damage scale was decreased from 26 km (mean) to 1.2 km (mean) significantly. The damage scale that exceed the thyroid dose criteria was decreased to 2~3 km (mean). The STC-4 damage scale was also decreased significantly as compared to STC-3, STC-6 in terms of effective dose.

Study on the Effectiveness of Radiological Technologist's Thyroid Shielding in Pediatric Paranasal Sinus X-ray Examination (어린이 부비동 엑스선 검사에서 검사자의 갑상선 차폐 효과성에 관한 연구)

  • Chang-Kyo Kwak;Jeong-Taek Kwon;Kwang-Je Lee;Il-Hwan Bae;Hye-Jung Kim;So-Mi Lee;Do-Byung Rhee
    • Journal of radiological science and technology
    • /
    • v.47 no.3
    • /
    • pp.197-203
    • /
    • 2024
  • During paranasal sinus X-ray examinations in children, the radiological technologist's thyroid shield is often not implemented to shorten the examination time. This study measured the radiation exposure before and after the implementation of thyroid shielding by analyzing the difference in radiation exposure, the radiological technologist's could receive depending on the actual thyroid shielding. In the left TLD, when thyroid shielding was not performed(N), the radiation exposure dose(mSv) was 2.869 for the depth dose[Hp(10)] and 2.886 for the surface dose[H(3)], and when thyroid shielding was performed(Y), the Hp(10) was 0.033 and the H(3) was 0.034. In the right TLD, when thyroid shielding was not performed(N), the radiation exposure dose was 3.149 for Hp(10) and 3.137 for H(3), and when thyroid shielding was performed, the Hp(10) of (Y) was 0.013 and the H(3) was 0.015. The differences in the overall exposure dose measurement values are all statistically significant (p<0.05). The difference in radiation dose between when thyroid shielding was not performed and when thyroid shielding was performed was more than 99.2% in both cases, indicating a high radiation shielding rate.

Evaluation of Scattered Rays of Jelly Type Shielding Body by L-spine AP using X-ray (L-Spine X-선 촬영에서의 Jelly type 차폐체의 산란선 차폐평가)

  • Jang, Hui-Min;Kim, Do-Gwon;Kim, Hyeong-Bin;Yoon, Joon
    • Journal of the Korean Society of Radiology
    • /
    • v.14 no.7
    • /
    • pp.907-913
    • /
    • 2020
  • There have been continuous controversies on medical X-ray protection and numerous researchers have been trying to prevent unnecessary exposure to radiation. As X-ray passes through the patient and obtains an image, it creates scattered ray due to interactions such as photoelectric effect and Compton scattering with the subject. As a result, both medical radiation staff and patient are exposed to unnecessary radiation on areas other than the target area. In response, this study will be assuming a body of a female, radiating X-ray on the phantom under the conditions of lumbar spine AP test, and measuring scattered ray around breasts and thyroid glands. Then, The experiment results were as follows. After application of non-shielding material, the average of scattered ray was 0.88 mR in thyroid measurement, 3.34 mR, Lt Axillary 3.54 mR, and Rt Axillary 3.03 mR in mamonary measurement but, After application of shielding material, the average of scattered ray was 0.16 mR in thyroid measurement, 0.60 mR, Lt Axillary 0.64 mR, and Rt Axillary 0.54 mR in mamonary measurement showing average scattered ray protection effect of about 82%. This study suggested the manufacturing method of a Jelly-type shielding material, identified the possibilities of researches on mixing various substances with radiology field, and verified the usability of the Jelly-type shielding material as a substitute for existing protection tools.

The Experience on Intake Estimation and Internal Dose Assessment by Inhalation of Iodine-131 at Korean Nuclear Power Plants (국내 원전에서 $^{131}I$ 내부 흡입 에 따른 섭취량 산정과 내부피폭 방사선량 평가 경험 몇 개선방향에 대한 연구)

  • Kim, Hee-Geun;Kong, Tae-Young
    • Journal of Radiation Protection and Research
    • /
    • v.34 no.3
    • /
    • pp.129-136
    • /
    • 2009
  • During the maintenance period at Korean nuclear power plants, internal exposure of radiation workers occurred by the inhalation of $^{131}I$ released to the reactor building when primary system opened. The internal radioactivity of radiation workers contaminated by $^{131}I$ was measured using a whole body counter. Intake estimation and the calculation of committed effective dose were also conducted conforming to the guidance of internal dose assessments from publications of International Commission on Radiological Protection. Because the uptake and excretion of $^{131}I$ in a body occur quickly and $^{131}I$ is accumulated in the thyroid gland, the estimated intakes showed differences depending on the counting time after intake. In addition, since ICRP publications do not provide the intake retention fraction (IRF) for whole body of $^{131}I$, the IRF for thyroid was substitutionally used to calculate the intake and subsequently this caused more error in intake estimation. Thus, intake estimation and the calculation of committed effective dose were conducted by manual calculation. In this study, the IRF for whole body was also calculated newly and was verified. During this process, the estimated intake and committed effective dose were reviewed and compared using several computer codes for internal dosimetry.