• Title/Summary/Keyword: ICRP103

Search Result 27, Processing Time 0.023 seconds

Application of the Two-Dosimeter Algorithm for Effective Dose Evaluations based on ICRP Publication 103 (ICRP 103 방사선방호 체계 하에서 유효선량 평가를 위한 Two-Dosimeter Algorithm의 적용방안)

  • Kim, Hee-Geun;Kong, Tae-Young
    • Journal of Radiation Protection and Research
    • /
    • v.36 no.3
    • /
    • pp.154-159
    • /
    • 2011
  • To evaluate the radiation exposure of workers participating in task where high radiation exposure is expected, two-dosimeter is typically provided radiation workers, one on the chest and the other on the back, at Korean nuclear power plants (NPPs). In a previous study, the NCRP (55:50) algorithm was selected as the optimal two-dosimeter algorithm (TDA) with various field tests and this TDA has been applied to all Korean NPPs since 2006. In 2007, the International Commission on Radiological Protection (ICRP) published the new ICRP recommendation, ICRP 103, which provides the revised weighting factors for both radiation and tissues and the new reference phantom. In this study, the applicability of current NCRP (55:50) algorithm at Korean NPPs for ICRP 103 was analyzed. As a result, it was found that the NCRP (55:50) algorithm is still effective to estimate the effective dose of workers under ICRP 103.

A Study on the Implementation of Dose Constraints in Occupational Dose According to ICRP 103 Recommendations in Korea (ICRP신권고에 따른 직무피폭에서의 선량제약치 국내 적용 방안 연구)

  • Kim, Yong-Min;Cho, Kun-Woo
    • Journal of Radiation Protection and Research
    • /
    • v.36 no.3
    • /
    • pp.127-133
    • /
    • 2011
  • In 2007, the International Commission on Radiological Protection (ICRP) published Recommendations of the International Commission on Radiological Protection. Accordingly IAEA safety standards committees have reviewed and revised the BSS. The process of the implementation of the ICRP 103 into Korean radiation protection regulations has been continued. Although the new recommendations retain the fundamental protection principles, the impact of the new ICRP recommendations will necessarily be greater than ever before. ICRP recommends the application of dose constraint in planned situations and reference level in existing & emergency situations for strengthening of the principle of optimization. Dose constraints and reference level play a criterion on the level of individual dose as prospective and source-related values. Therefore it is necessary to apply dose constraints and reference levels to all nuclear and RI&RG facilities in Rep. of Korea. Dose constraints and reference level of occupational exposure will be set-up by the stakeholder itself with the cooperation of regulatory body. In this study, the implementation method was discussed to apply the dose constraints and reference level as the procedure for the optimization, not the tool of the regulation.

A Preliminary Establishment of Dose Constraints for the Member of Public Taking into Account Multi-unit Nuclear Power Plants in Korea (국내 복수호기 원전 운영을 고려한 일반인 선량제약치 설정에 대한 고찰)

  • Kong, Tae-Young;Choi, Jong-Rack;Son, Jung-Kwon;Kim, Hee-Geun
    • Journal of Radiation Protection and Research
    • /
    • v.37 no.3
    • /
    • pp.129-137
    • /
    • 2012
  • In the 2007 recommendation, the ICRP evolves from the previous process-based system of practices and intervention to the system based on the characteristics of radiation exposure situation. In addition, ICRP recommends the application of source-related dose constraints under the planned exposure situation as a tool for the optimization of protection to workers and the member of public. In this study, the analysis of radioactive effluents from Korean nuclear power plants and the public dose assessment were conducted in reference with the use of dose constraints. Finally, the measure to implement the dose constraints for the member of public was suggested taking into account multi-unit reactors operating at a single site in Korea.

Evaluation of Photoneutron Dose in Radiotherapy Room Using MCNPX (MCNPX를 이용한 방사선 치료실의 광중성자 선량 평가)

  • Park, Eun-Tae
    • The Journal of the Korea Contents Association
    • /
    • v.15 no.6
    • /
    • pp.283-289
    • /
    • 2015
  • Recently, high energy photon radiotherapy is a growing trend for increasing therapy results. Commonly, if you use high energy photons above 6~8 MeV nominal accelerator voltage, It lead the photo-nuclear reaction and the generation of photo-neutron are accompanied and these problematic factors are issued in the view of radiation protection. Therefore, in this study analyzed for dose distribution of photo-neutron in radiotherapy room based on MCNPX. As a result, absorbed dose is increased sharply from 10 MV to 12 MV. It was founded that the rapid increasement of photoneutron fluence was related to the absorbed dose at above 10 MV. Also, in case of the recommendation of ICRP 103, the outcome of an exchanged equivalent dose which based on calculated an absorbed dose, showed lower equivalent dose than ICRP 60 by reflecting the contribution of secondary photon for absorbed dose of human body in the low energy band.

Assessment of Effective Dose for General Radiography of Adults Based on Diagnostic Reference Level(DRL) by Using PCXMC Program (진단참고준위(DRL)를 기준으로 PCXMC 프로그램을 이용한 성인의 일반촬영 부위별 유효선량 평가)

  • Jeong, Hee-Cheol;Lee, SamYol
    • Journal of the Korean Society of Radiology
    • /
    • v.12 no.7
    • /
    • pp.807-812
    • /
    • 2018
  • In this study, we investigated the conditions used in setting the recommendation level of general radiography diagnostic reference and tried to evaluate the effective dose and biological evaluation using PCXMC v2.0 program. As a result based on the effective dose of male in ICRP 60, the highest Pelvis AP was 0.794 mSv. The lowest Chest PA was 0.050 mSv. In the case of ICRP 103, the highest T-Spine AP was 0.906 mSv The lowest Chest PA was 0.052 mSv. For 40 years old male and female adults, effective doses of general radiography were evaluated and even if the medical exposures are not subject to the limit of dose, efforts should be made to reduce the medical exposures of the people by keeping the dose below the recommended amount in order to minimize the probable effect of radiation hazard.

Development of the Monte Carlo Simulation Radiation Dose Assessment Procedure for NORM added Consumer Adhere·Non-Adhere Product based on ICRP 103 (ICRP 103 권고기반의 밀착형·비밀착형 가공제품 사용으로 인한 몬테칼로 전산모사 피폭선량 평가체계 개발)

  • Go, Ho-Jung;Noh, Siwan;Lee, Jae-Ho;Yeom, Yeon-Soo;Lee, Jai-Ki
    • Journal of Radiation Protection and Research
    • /
    • v.40 no.3
    • /
    • pp.124-131
    • /
    • 2015
  • Radiation exposure to humans can be caused by the gamma rays emitted from natural radioactive elements(such as uranium, thorium and potassium and any of their decay products) of Naturally Occurring Radioactive Materials(NORM) or Technologically Enhanced Naturally Occurring Radioactive Materials(TENORM) added consumer products. In this study, assume that activity of radioactive elements is $^{238}U$, $^{235}U$, $^{232}Th$ $1Bq{\cdot}g^{-1}$, $^{40}K$ $10Bq{\cdot}g^{-1}$ and the gamma rays emitted from these natural radioactive elements radioactive equilibrium state. In this study, reflected End-User circumstances and evaluated annual exposure dose for products based on ICRP reference voxel phantoms and ICRP Recommendation 103 using the Monte Carlo Method. The consumer products classified according to the adhere to the skin(bracelet, necklace, belt-wrist, belt-ankle, belt-knee, moxa stone) or not(gypsum board, anion wallpaper, anion paint), and Geometric Modeling was reflected in Republic of Korea "Residential Living Trend-distributions and Design Guidelines For Common Types of Household.", was designed the Room model($3m{\times}4m{\times}2.8m$, a closed room, conservatively) and the ICRP reference phantom's 3D segmentation and modeling. The end-user's usage time assume that "Development and Application of Korean Exposure Factors." or conservatively 24 hours; in case of unknown. In this study, the results of the effective dose were 0.00003 ~ 0.47636 mSv per year and were confirmed the meaning of necessary for geometric modeling to ICRP reference phantoms through the equivalent dose rate of belt products.

Reading and Influence of Personal Dose Meter in University Hospital C (C 대학병원의 개인선량계 판독과 영향)

  • Lee, Joo-Ah
    • Journal of the Korean Society of Radiology
    • /
    • v.16 no.3
    • /
    • pp.357-363
    • /
    • 2022
  • This study aims to improve the safety inspection awareness of occupational exposure and help radiation safety management by analyzing radiation exposure doses by occupational type of radiation related-workers and radiation workers. Radiation-related workers and radiation workers were classified into three occupations (radiological technologist, doctors, and nurses). A nominal risk coefficient based on ICRP 103 was used to calculate the probability of causing side effects of the lungs due to exposure doses. As a result of analyzing the exposure dose of all workers for one year, the exposure dose of radiological technologist among radiation-related workers was 1.63 ± 2.84 mSv, doctors 0.12 ± 0.22 mSv, and nurses 0.59 ± 1.08 mSv. The one-year deep dose for radiation workers was 2.44 ± 3.30 mSv for radiological technologists, 0.19 ± 0.26 mSv for doctors, and 0.12 ± 0.00 mSv for nurses. Due to this dose, the probability of causing side effects in the lungs was 1.2 per 100,000 radiological technologist, 0.096 doctors, and 0.06 nurses. In this study, it is believed that the probability of side effects on lungs by occupation of radiation exposure dose will be studied and used as useful data for radiation safety management in relation to probabilistic effects in the future.

A Study on the Radiation Exposure Dose of Clinical Trainees in the Department of Radiology: A Case Study at C University Hospital (방사선(학)과 임상실습생의 수시출입자 피폭선량에 대한 고찰: C 대학병원 사례 연구)

  • Joo-Ah Lee
    • Journal of the Korean Society of Radiology
    • /
    • v.17 no.2
    • /
    • pp.249-255
    • /
    • 2023
  • In this study, radiation exposure doses were measured in the course of clinical practice of radiation workers, radiological technologists in the radiation-related worker group, and preliminary-radiological technologists who were classified as frequent visitors. Radiological technologists who worked in the radiation area of C University Hospital in Incheon for a year from January 2021 and 121 students who completed clinical practice at the same medical institution from July 1 to August 31 were the subjects of the study. The nominal risk factor based on ICRP 103 was used to evaluate the probability of side effects due to the exposure dose to the lungs, which are organs at risk of damage due to radiation exposure dose. During the clinical practice period, radiology students, who were classified as frequent visitors, had a surface dose of 0.98 ± 0.14 mSv and a deep dose of 0.93 ± 0.14 mSv. In other words, 6.7 per 1,000,000 for shallow dose and 6.4 per 1,000,000 for deep dose were found to have side effects due to exposure to the lungs. This is a value in terms of exposure dose in one year. Considering that the radiation (science) education course is 3 or 4 years, systematic management and attention to prospective radiation workers who are going to clinical practice are required, and the stochastic effect of radiation In relation to this, it is considered that it will be used as basic data for radiation safety management.

New thyroid models for ICRP pediatric mesh-type reference computational phantoms

  • Yeon Soo Yeom ;Chansoo Choi ;Bangho Shin ;Suhyeon Kim ;Haegin Han ;Sungho Moon ;Gahee Son;Hyeonil Kim;Thang Tat Nguyen;Beom Sun Chung;Se Hyung Lee ;Chan Hyeong Kim
    • Nuclear Engineering and Technology
    • /
    • v.54 no.12
    • /
    • pp.4698-4707
    • /
    • 2022
  • As part of the ICRP Task Group 103 project, we developed ten thyroid models for the pediatric mesh-type reference computational phantoms (MRCPs). The thyroid is not only a radiosensitive target organ needed for effective dose calculation but an important source region particularly for radioactive iodines. The thyroid models for the pediatric MRCPs were constructed by converting those of the pediatric voxel-type reference computational phantoms (VRCPs) in ICRP Publication 143 to a high-quality mesh format, faithfully maintaining their original topology. At the same time, we improved several anatomical parameters of the thyroid models for the pediatric MRCPs, including the mass, overlying tissue thickness, location, and isthmus dimensions. Absorbed doses to the thyroid for the pediatric MRCPs for photon external exposures were calculated and compared with those of the pediatric VRCPs, finding that the differences between the MRCPs and VRCPs were not significant except for very low energies (<0.03 MeV). Specific absorbed fractions (target ⟵ thyroid) for photon internal exposures were also compared, where significant differences were frequently observed especially for the target organs/tissues close to the thyroid (e.g., a factor of ~1.2-~327 for the thymus as a target) due mainly to anatomical improvement of the MRCP thyroid models.