• Title/Summary/Keyword: 집단선량

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The Assessment of Exposure Dose of Radiation Workers for Decommissioning Waste in the Radioactive Waste Inspection Building of Low and Intermediate-Level Radioactive Waste Disposal Facility (경주 중·저준위방사성폐기물 처분시설의 방폐물검사건물에서 해체 방사성폐기물 대상 방사선작업종사자의 피폭선량 평가 및 작업조건 도출)

  • Kim, Rin-Ah;Dho, Ho-Seog;Kim, Tae-Man;Cho, Chun-Hyung
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.18 no.2_spc
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    • pp.317-325
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    • 2020
  • The Korea Radioactive Waste Agency plans to expand the storage capacity of radioactive waste by constructing a radioactive waste inspecting building to solve the problem of the lack of inspection space and drum-handling space in the radioactive waste receipt and storage building for the first-stage disposal facility. In this study, the exposure doses of radiation workers that handle new disposal containers for decommissioning waste in the storage areas of the radioactive waste inspecting building were calculated using the Monte Carlo N-particle transport code. The annual collective dose was calculated as a total of 84.8 man-mSv for 304 new disposal containers and an estimated annual 306 working hours for the radiation work. When the 304 new disposal containers (small/medium type) were stored in the storage areas, it was found that 25 radiation workers should be involved in acceptance/disposal inspection, and the estimated exposure dose per worker was calculated as an average annual value of 3.39 mSv. When the radiation workers handle the small containers in high-radiation dose areas, the small containers should be shielded further by increasing the concrete liner thickness to improve the work efficiency and radiation safety of the radiation workers. The results of this study will be useful in establishing the optimal radiation working conditions for radiation workers using the source term and characteristics of decommissioning waste based on actual measurements.

Residual Radioactivity Investigation & Radiological Assessment for Self-disposal of Concrete Waste in Nuclear Fuel Processing Facility (콘크리트 폐기물의 자체처분을 위한 잔류방사능 조사 및 피폭선량평가)

  • Seol, Jeung-Gun;Ryu, Jae-Bong;Cho, Suk-Ju;Yoo, Sung-Hyun;Song, Jung-Ho;Baek, Hoon;Kim, Seong-Hwan;Shin, Jin-Seong;Park, Hyun-Kyoun
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.5 no.2
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    • pp.91-101
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    • 2007
  • In this study, domestic regulatory requirement was investigated for self-disposal of concrete waste from nuclear fuel processing facility. And after self-disposal as landfill or recycling/reuse, the exposure dose was evaluated by RESRAD Ver. 6.3 and RESRAD BUILD Ver.3.3 computing code for radiological assessments of the general public. Derived clearance level by the result of assessments for the exposure dose of the general public is 0.1071Bq/g (3.5% enriched uranium) for landfill and $0.05515Bq/cm^2$ (5% enriched uranium) for recycling/reuse respectively. Also, residual radioactivity of concrete waste after decontamination was investigated in this study. The result of surface activity is $0.01Bq/cm^2\;for\;{\alpha}-emitter$ and the result of radionuclide analysis for taken concrete samples from surface of concrete waste is 0.0297Bq/g for concentration of $^{238}U$, below 2w/o for enrichment of $^{235}U$ and 0.0089Bq/g for artificial contamination of $^{238}U$ respectively. Therefore, radiological hazard of concrete waste by self-disposal as landfill and recycling/reuse is below clearance level to comply with clearance criterion provided for Notice No.2001-30 of the MOST and Korea Atomic Energy Act.

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A Study on the Food Consumption Rates for Off-site Radiological Dose Assessment around Korean Nuclear Power Plants (국내 원자력발전소 주변 주민의 방사선량 평가를 위한 음식물 섭취율 설정 연구)

  • Lee, Gab-Bock;Chung, Yang-Geun
    • Journal of Radiation Protection and Research
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    • v.33 no.4
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    • pp.183-196
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    • 2008
  • The internal dose by food consumption mostly accounts for radiological dose of public around nuclear power plants (NPPs). But, food consumption rates applied to off-site dose calculation in Korea which are the result of field investigation around Kori NPP by the KAERI (Korea Atomic Energy Research Institute) in 1988, are not able to reflect the latest dietary characteristics of Korean. The food consumption rates to be used for radiological dose assessment in Korea are based on the maximum individual of US NRC (Nuclear Regulatory Commssion) Regulatory Guide 1.109. However, the representative individual of the critical group is considered in the recent ICRP (International Commission on Radiological Protection) recommendation and European nations' practice. Therefore, the study on the re-establishment of the food consumption rates for individual around nuclear power plant sites in Korea was carried out to reflect on the recent change of the Korean dietary characteristics and to apply the representative individual of critical group to domestic regulations. The Ministry of Health and Welfare Affairs has investigated the food and nutrition of nations every 3 years based on the Law of National Health Improvement. The statistical data such as mean, standard deviation, various percentile values about food consumption rates to be used for the representative individual of the critical group were analyzed by using the raw data of the national food consumption survey in $2001{\sim}2002$. Also, the food consumption rates for maximum individual are re-estimated.

Caregiver or Family Doses due to Discharged $^{131}I$ Administrated Patient from the Hospital (고용량 $^{131}I$ 투여환자 퇴원이후 환자 간병인과 환자 가옥의 피폭선량 측정)

  • Jeong, Gyu-Hwan;Lee, Hyun-Kook;Cho, Woon-Kap;Lee, Jai-Ki
    • Journal of radiological science and technology
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    • v.33 no.2
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    • pp.149-154
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    • 2010
  • Exposed doses to the patient's caregiver and their house due to the 131I from patients discharged from the hospital were measured using OSL dosimeters. Usually, 3.37-5.55 GBq (100-150 mCi) of $^{131}I$ administrated patients are discharged from the hospital after 3 or 4 days of hospitalization in Korea. In addition, after 5 to 8 days, the accumulated doses of the patient's caregiver and house after hospitalization of the patient were measured using OSL dosimeters. The results of the measured average accumulated doses were 0.1 mSv, which is 10% of 1 mSv, the public dose limit in the Korean Atomic Energy Law. And it's standard deviation was 0.087 mSv. Based on the results of this study, we anticipate that we could assure the compliance of the regulation requirement 5 mSv of MEST (Ministry of Education, Science and Technology) Notice No. 2008-45 for the patient's caregiver or family, even if we reduce the 3-4 days of hospitalization to 1-2 days or less.

Developments in Radiation Health Science and Their Impact on Radiation Protection (방사선 보건과학의 발전과 방사선방호에 미치는 영향)

  • Chang, Si-Young;Kim, In-Gyoo
    • Journal of Radiation Protection and Research
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    • v.23 no.3
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    • pp.185-196
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    • 1998
  • 현재의 방사선방호 원칙과 체계는 국제방사선방호위원회 (ICRP)의 권고에 기반을 두고 있 다. ICRP 의 권고는 대부분 히로시마/나카사키 원폭피해 생존자들에 대한 역학조사 및 수명 연구결과 그리고 관련 방사선생물학 연구결과를 바탕으로 전세계 5개 인구집단(일본, 미국, 푸에리토리코, 영국과 중국)에 대한 방사선위험계수의 예측 및 평가결과에 근거를 두고 있다. 이 저선량 방사선의 (확률적 영향) 위험계수는 인체피폭 방사선량과 그 영향간에는 선형 비례관계가 있으며 영향유발의 문턱값이 존재하지 않는다는 가정인 '선형 무문턱값 선량-영향 모델 (Linear No-Threshold Dose-Effect Model, 이른바 LNT 모텔)' 을 도입하여 유도된 것이다(譯者 밑줄). 그러나 이 LNT 가정의 과학적 근거와 정당성에 대한 비난이 원자력산업계나 일부 과학자들에 의해 제기된 이래, 최근에는 미국 보건물리학회 (HPS)에서 'LNT 가정이 선량과 영향의 관계를 단순화하며 낮은 선량의 위험음 과대평가한다'는 성명서를 발표하기도 했다. 이후 이에 대한 논쟁이 다시 시작되어, 1997 년에 스페인의 Sevill에서는 IAEA와 WHO의 공동주최와 UNSCEAR의 협조로 '저준위 방사선 영향에 대한 국제회의'가 개최되기도 하였으나 아직 어느 쪽에도 유리한 결론이 단정적으로 나지 않았으며, 실질적인 대안이 없는 현실에서 이 LNT 가정은 여전히 방사선방호의 철학적 기초로 남아 있다(譯者 밑줄). 한편, 저선량 방사선의 영향에 대해서는 우리나라에서도 '방사선방어학회, ‘98 년 춘계 심포지움' 및 '원자력학회, '98 년 춘계 학술발표회 워크??????'에서 한양대학교의 이재기 교수에 의하여 소개, 논의된 바 있다.이 논문은 이러한 논의의 후속으로 역자중 일인이 위원으로 있는 OECD/NEA 방사선방호위원회 (CRPPH)가 최근에 ('98.7.) 발간한 보고서를 번역, 주해한 것으로, 과학지식의 진보에 따라 방사선방호분야에서 관심이 되는 주제들에 대한 위원회의 검토의견을 소개하고 있다. 따라서 이 논문이 국내의 방사선방호분야 관계자들에게 최신정보 습득과 지식함양에 좋은 도움이 되기를 기대한다.

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Application of Low-Dose CT for Screening of Lung Disease (폐질환의 선별검사를 위한 저선량 전산화 단층촬영의 적용)

  • Lee, Won-Jeong;Choi, Byung-Soon;Park, Young-Sun;Seon, Jong-Ryul;Bae, Seok-Hwan
    • Journal of radiological science and technology
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    • v.32 no.2
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    • pp.129-140
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    • 2009
  • As CT has been increasingly used as an accurate screening tool for lung disease, radiation dose becomes an important issue for both radiographers and patients. Many researches have been done for a low-dose CT as a screening tool for early detection of asymptomatic lung diseases. From those studies, it has been reported that chest dose rate from the low-dose CT is considerably lower than from standard CT. The patient dose is determined by scanning parameters such as kVp, mAs, pitch, scan time and the radiation risk of lung in screening examination may not be negligible. Herein, we suggest that Low-dose CT is useful as a screening tool in routine clinical practice on the basis of published articles, but further study is necessary because Low-dose CT has poor sensitivity and specificity for screening early stage of lung cancer according to the results of the studies. This article is to provide a brief overview of the screening examinations by Low-dose CT.

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Proposal for Management of Small Reservoirs (기술사 마당 - 소규모 저수지 관리를 위한 제언)

  • Koo, Bon-Chung
    • Journal of the Korean Professional Engineers Association
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    • v.45 no.4
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    • pp.62-66
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    • 2012
  • An effective management of reservoir, an agricultural infrastructure, requires an establishment of a good management system by means of unification of managing entity; training of manpower and their deployment for scientific management by expert group; carrying out repair / strengthening works based on periodic in-depth inspection results. In particular, continuous budget allocation as well as cultivating good management mind of managing entity are essential for undertaking periodic precise and / or in-depth inspections for assessing the functionality / safety of facilities and proper repair / strengthening works for satisfying the up-to-date facilty standarda and changing environmental conditions.

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Prediction of Obstructive Coronary Artery Disease by Coronary Artery Calcification Finding on Low-dose CT Image for screening of lung diseases: Compared with Calcium Scoring CT (폐질환 선별검사를 위한 저선량 CT영상의 관상동맥 석회화 소견으로부터 폐쇄성 관상동맥질환 예측: 석회화수치 CT검사와 비교)

  • Lee, Won-Jeong
    • The Journal of the Korea Contents Association
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    • v.11 no.10
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    • pp.333-341
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    • 2011
  • To compare between calcium scoring CT (CSCT) and Low-dose CT (LDCT) image finding for coronary artery calcification (CAC) in screening of lung disease by MDCT. A total of 61 subjects who retired-workers exposed to inorganic dust were performed LDCT and CSCT by using a MDCT scanner on the same day, after be approved by the institutional review board, and obtaining the written informed consent from all subjects. LDCT images were read for detecting lung diseases as well as CAC by a experienced chest radiologist, then the subjects were divided either the positive group with CAC or the negative group without it. The CSCT was used to quantify and detect the presence of calcification in the coronary artery, and score of CAC calculated by using a Rapidia software (ver 2.8). In all coronary arteries, calcium score of positive group was higher better than that in negative group, especially in the total calcium (13.7 vs. 582.9, p=0.008) and the left anterior descending artery (3.2 vs. 249.0, p=0.006). CAC findings between CSCT and LDCT image were showed excellent agreement in cut-off point 100(K-value=0.80, 95% CI=0.69-0.91) from total calcium score. CAC findings on LDCT images showed the higher relation with CSCT. Therefore, the obstructive coronary artery disease could be predicted by CAC on LDCT images for screening of lung diseases.

KAERI 폐 카운터를 이용한 LLNL 팬텀과 JAERI 팬텀과의 비교

  • 이종일;이태영;김종수;장시영
    • Proceedings of the Korean Nuclear Society Conference
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    • 1998.05b
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    • pp.600-605
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    • 1998
  • 체내방사능 측정시스템의 교정인자는 측정결과에 주요한 요인으로 작용한다. 교정인자는 특정 집단으로부터 표준체위와 표준장기를 도출, 이를 기초로 하여 제작한 펜텀으로부터 구하는 것이 일반적인 방법이다. 그러나 팬텀의 기하학적 구조 및 내부장기의 형상은 특정 집단에 따라 다르므로 이로 인한 측정오차가 발생할 수 있다. 따라서 본 연구에서는 북아메리카 성인남성의 표준자료에 근거하여 제작된 LLNL 팬텀과 일본성인 남성의 표준자료에 근거하여 제작된 JAERI 팬텀을 한국원자럭연구소 폐 카운터를 이용하여 상호비교.분석하였다. 이와 함께 LLNL 팬텀으로 교정된 폐 카운터의 성능시험을 JAERI 팬텀으로 DOELAP 성능시험범주 I, II, III 및 IV에 대해 수행하여 편텀의 구조 및 형상으로부터 발생하는 측정오차를 분석하였다. 비교.분석결과 1.7 cm ~ 3.7 cm 근육등가 가슴벽두께 범위내에서 JAERI 팬텀에 의한 교정인자가 전반적으로 LLNL 팬텀의 것보다 다소 높은 수치를 보였으나 허용수준이었고, 성능시험결과 상대편중은 DOELAP 성능 용인 기준을 만족하였다. 결국 두 팬텀간의 측정오차는 측정 및 체내피폭선량 평가시 수반되는 오차와 비교해 보면 그다지 크지 않은 것으로 결론지울 수 있다. 따라서 LLNL 펜텀으로부터 구한 교정인자를 국내 성인남성의 일상 모니터링에 사용할 경우 측정결과가 다소 과대평가되기는 하나 허용수준으로서 큰 문제가 없는 것으로 나타났다.

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A Study to Decrease Exposure Dose for the Radiotechnologist in PET/CT (PET/CT 검사에서 방사선 종사자 피폭선량 저감에 대한 방안 연구)

  • Cho, Seok-Won;Park, Hoon-Hee;Kim, Jung-Yul;Ban, Yung-Kak;Lim, Han-Sang;Oh, Ki-Beak;Kim, Jae-Sam;Lee, Chang-Ho
    • The Korean Journal of Nuclear Medicine Technology
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    • v.14 no.2
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    • pp.159-165
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    • 2010
  • Purpose: Positron emission tomography scan has been growing diagnostic equipment in the development of medical imaging system. Compare to $^{99m}Tc$ emitting 140 keV, Positron emission radionuclide emits 511 keV gamma rays. Because of this high energy, it needs to reduce radioactive emitting from patients for radiotechnologist. We searched the external dose rates by changing distance from patients and measure the external dose rates when we used shielder investigate change external dose rates. In this study, the external dose distribution were analyzed in order to help managing radiation protection of radiotechnologists. Materials and Methods: Ten patients were searched (mean age: $47.7{\pm}6.6$, mean height: $165.5{\pm}3.8$ cm and mean weight: $65.9{\pm}1.4$ kg). Radiation were measured on the location of head, chest, abdomen, knees and toes at the distance of 10, 50, 100, 150 and 200 cm. Then, all the procedure was given with a portable radiation shielding on the location of head, chest and abdomen at the distance of 100, 150 and 200 cm and transmittance was calculated. Results: In 10 cm, head (105.40 ${\mu}Sv/h$) was the highest and foot (15.85 ${\mu}Sv/h$) was the lowest. In 200 cm, head, chest and abdomen showed similar. On head, the measured dose rates were 9.56 ${\mu}Sv/h$, 5.23 ${\mu}Sv/h$, and 3.40 ${\mu}Sv/h$ in 100, 150 and 200 cm respectively. When using shielder, it shows 2.24 ${\mu}Sv/h$, 1.67 ${\mu}Sv/h$, and 1.27 ${\mu}Sv/h$ in 100, 150 and 200 cm on head. On chest, the measured dose rates were 8.54 ${\mu}Sv/h$, 4.90 ${\mu}Sv/h$, 3.44 ${\mu}Sv/h$ in 100, 150 and 200 cm, respectively. When using shielder, it shows 2.27 ${\mu}Sv/h$, 1.34 ${\mu}Sv/h$, and 1.13 ${\mu}Sv/h$ in 100, 150 and 200 cm on chest. On abdomen, the measured dose rates were 9.83 ${\mu}Sv/h$, 5.15 ${\mu}Sv/h$ and 3.18 ${\mu}Sv/h$ in 100, 150 and 200cm respectively. When using shielder, it shows 2.60 ${\mu}Sv/h$, 1.75 ${\mu}Sv/h$ and 1.23 ${\mu}Sv/h$ in 100, 150 and 200 cm on abdomen. Transmittance was increased as the distance was expanded. Conclusion: As the distance was further, the radiation dose were reduced. When using shielder, the dose were reduced as one-forth of without shielder. The Radio technologists are exposed of radioactivity and there were limitations on reducing the distance with Therefore, the proper shielding will be able to decrease radiation dose to the radiotechnologists.

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