• Title/Summary/Keyword: Radiological Protection

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Radioprotective Effects of Propolis on the Mouse Testis Exposed to X-ray. (프로폴리스가 X-선에 노출된 마우스 정소에 미치는 방사선 방어 효과)

  • Ji, Tae-Jung;Kim, Jong-Sik;Jeong, Hyung-Jin;Seo, Eul-Won
    • Journal of Life Science
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    • v.17 no.5 s.85
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    • pp.664-670
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    • 2007
  • The propolis is natural product produced by honeybees and is known to have many biologically useful properties such as anti-microbial, anti-oxidative and anti-tumorigenic activity. However, its radio-protective property has not been well studied. To investigate radio-protective effect of propolis on mouse testis, mice were supplemented with propolis after 5 Gy irradiation. The histological changes of testis were detected by TEM. The results indicate that propolis may protect tissue deformation which is induced by 5 Gy of ionizing radiation. Furthermore, to elucidate the potential molecular mechanisms involved in radio-protective property of propolis, we performed microarray experiments using oligo DNA microarray. We found 65 up-regulated genes and 224 down-regulated genes, whose expression levels were affected more than 2-fold by propolis treatment in mice irradiated at 5 Gy. We confirmed microarray data with reverse transcription-PCR using gene specific primers. The results of RT-PCR are highly correlated with those of microarray. These results may help understanding molecular mechanisms of radioprotective effects by propolis in mouse model.

Health Risk Assessment due to 137Cs Released into Ocean from the Severe Accident of the Fukushima Dai-ichi Nuclear Power Plants (후쿠시마 사고로 해양으로 누출된 137Cs에 의한 인체 위해도 평가)

  • Min, Byung Il;Lee, Baek Gun;Suh, Kyung Suk;Park, Kihyun
    • Journal of Radiation Industry
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    • v.8 no.2
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    • pp.123-132
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    • 2014
  • After the nuclear accident of the Fukushima Dai-ichi Nuclear Power Plants (FDNPPs) on 11 March 2011, a large amount of radioactive materials has been released into the atmosphere and the ocean. A compartment model is used to evaluate the circulation characteristics and the spatiotemporal concentration distributions of radionuclides in the ocean. In the comparison with observed concentrations of $^{137}Cs$ in seawater, calculated concentrations by the compartment model were well agreed with them. On the basis of these results, we performed evaluation of the effective dose and the cancer risk. In the early stage of the accident, the effective doses from ingestion of the seafood near the Fukushima region were much higher than 1 mSv which is the value of the annual effective dose limit to individual recommended by the International Commission on Radiological Protection (ICRP). However, the effective doses by ingestion of the seafood decreased below 1 mSv as distance from the FDNPPs increased and time passed. In addition, it was estimated that the cancer risks by intake of the contaminated marine products were less than natural occurrence probability of cancer. Consequently, it was inferred that the health risk due to the $^{137}Cs$ was low after since mid-term period of the accident.

POWER UPRATES IN NUCLEAR POWER PLANTS: INTERNATIONAL EXPERIENCES AND APPROACHES FOR IMPLEMENTATION

  • Kang, Ki-Sig
    • Nuclear Engineering and Technology
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    • v.40 no.4
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    • pp.255-268
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    • 2008
  • The greater demand for electricity and the available capacity within safety margins in some operating NPPs are prompting nuclear utilities to request license modification to enable operation at a higher power level, beyond their original license provisions. Such plant modifications require an in-depth safety analysis to evaluate the possible safety impact. The analysis must consider the thermo hydraulic, radiological and structural aspects, and the plant behavior, while taking into account the capability of the structures, systems and components, and the reactor protection and safeguard systems set points. The purpose of this paper is to introduce international experiences and approaches for implementation of power uprates related to the reactor thermal power of nuclear power plants. The paper is intended to give the reader a general overview of the major processes, work products, issues, challenges, events, and experiences in the power uprates program. The process of increasing the licensed power level of a nuclear power plants is called a power uprate. One way of increasing the thermal output from a reactor is to increase the amount of fissile material in use. It is also possible to increase the core power by increasing the performance of the high power bundles. Safety margins can be maintained by either using fuels with a higher performance, or through the use of improved methods of analysis to demonstrate that the required margins are retained even at the higher power levels. The paper will review all types of power uprates, from small to large, and across various reactor types, including light and heavy water, pressurized, and boiling water reactors. Generally, however, the content of the report focuses on power uprates of the stretch and extended type. The International Atomic Energy Agency (IAEA) is developing a technical guideline on power uprates and side effects of power uprates in nuclear power plants.

Evaluation of entrance surface dose and image quality according to the installation of Bismuth shield in the case of endovascular treatment of cerebral aneurysm (뇌동맥류 코일 색전술 시 Bismuth 차폐체 설치에 따른 입사 표면 선량 평가 및 화질 평가)

  • Kim, Jae-Seok;Kim, Young-Kil;Choi, Jae-Ho
    • Journal of the Korea Institute of Information and Communication Engineering
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    • v.23 no.7
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    • pp.779-785
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    • 2019
  • By applying an ergonomically developed Bismuth shield to the endovascular treatment of cerebral aneurysm the radiation dose of the scalp and lens from the medical radiation exposure was reduced. The enrtance surface dose was analyzed by measuring the occipital parts, bilateral temporal parts, bilateral quadriceps, and nasal tip of the developed bismuth shield using a photostimulable fluorescence dosimeter before (Group A) before use (Group B). Signal to noise ratio (SNR) and contrast to noise ratio (CNR) analysis were used to evaluate the image quality when Bismuth shielding was used. The mean entrance surface dose of A group and B group was 26.92% lower than that of A group. The analysis of CNR and SNR was the same for both Roadmap and DSA. The use of Bismuth shielding is an alternative that can reduce the radiation impairment due to temporary hair loss and other stochastic effects that may occur after cerebrovascular intervention.

Effective Doses Estimated According to Characteristics of Airborne Radon and Thoron Levels Generated from Some Household Products (일부 생활용품에서 발생한 공기 중 라돈과 토론의 발생 특성 및 연간 유효선량 추정)

  • Park, Dong-Uk;Yi, Seongjin;Kim, So-Yeon;Kwak, Hyunseok;Lee, Seunghee;Park, Jihoon
    • Journal of Environmental Health Sciences
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    • v.45 no.2
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    • pp.99-112
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    • 2019
  • Objective: This study aims to analyze the characteristics of airborne radon and thoron level ($Bq/m^3$) generated from household products containing monazites, and estimate the effective doses (mSv/yr). Method: Radon & Thoron detector EQF3220 was used to monitor real-time airborne radon and thoron level ($Bq/m^3$), and their daughters ($Bq/m^3$) were recorded every two hours. Effective doses (mSv/yr) for radon and thoron were estimated according to models developed by International Commission on Radiological Protection (ICRP) and United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR). Results: The average levels of radon and thoron were $87.8Bq/m^3$ (range; $20.8-156.3Bq/m^3$) and $1,347.5Bq/m^3$ (range; $4-5,839.7Bq/m^3$), respectively. The average equilibrium factors (F) were 0.23 and 0.007, respectively. The levels of radon progeny were far higher than that thoron. Latex mattress showed the highest F (0.38). The average effective doses were estimated to be ICRP (1.9 mSv/yr) and UNSCER (1.3 mSv/yr) for radon and UNSCEAR (1.6 mSv/yr) for thoron. Conclusions: Our results have far exceeded the allowable effective dose for general population (1 mSv/yr). The government's actions such as the ban of use of consumer products containing monazite and the establishment of surveillance system to evaluate health effects for the people affected should be taken as early as possible.

The Measurement of Spatial Dose Rate by Gravity Ventilation after Technegas Scanning (Technegas 스캐닝 후 중력환기에 의한 공간선량율 측정)

  • Kim, Sung-Bin;Won, Do-Yeon
    • Journal of the Korean Society of Radiology
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    • v.13 no.4
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    • pp.667-674
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    • 2019
  • Because examination with technegas produces images through simple diffusion accumulation, the examination room can become contaminated after scan. Therefore, radiation workers and patients awaiting examination will be affected by internal exposure from technegas inhalation. Before and after gravity ventilation, I am trying to find a way to reduce the exposure dose of waiting patients according to a comparative analysis of horizontal spatial dose rates over time. Spatial dose ratio were measured for 10 minutes from various distances and angles around ventilator's location before and after gravity ventilation. Then, mean values, standard deviation and reduction ratio were calculated. The highest reduction rate of gravity ventilation was 95.31% and the highest reduction ratio was 1 to 3 minutes. Therefore, the gravity ventilation could reduce the exposure dose of radiologic technologists, waiting patients, patient guardians and nurses. In conclusion, the reduction of the exposure dose during the technegas ventilation study through gravity ventilation will play a role in optimiging the protection and it is in accordance with the recommended reduction of the medical exposure by ICRP 103.

A Study on Laws Related to Anonymization of Medical Image Information in PACS (PACS에서 의료영상정보의 익명처리와 관련된 법의 연구)

  • Kweon, Dae Cheol
    • Journal of the Korean Society of Radiology
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    • v.16 no.5
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    • pp.627-637
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    • 2022
  • The purpose of this study is to comply with the operation and management of medical image information in PACS, the necessity of anonymizing the patient's personal information and the management status of the medical image information related to the personal The purpose of this study was to raise, discuss, and suggest the need for unification and coherence of the law by studying the content of the issues related to information related laws. In order to utilize information related to medical image information, it is necessary to unify the "Medical Act" or the "Bioethics Act" for clear legal application and consider the legal system's consistency. Since there is a possibility of conflict due to issues that are not yet established, systematic coherence of the law is required to find the basic common denominator for the utilization and use of medical image information and to harmonize the law. In addition, the necessity of enacting the "Medical Information Protection Act" that can be practically applied and easily practiced by medical personnel and managers in the clinical field so that sensitive matters of medical image information and personal information can be protected and managed in a specific and systematic way.

Physical characterization and radiation shielding features of B2O3-As2O3 glass ceramic

  • Mohamed Y. Hanfi;Ahmed K. Sakr;A.M. Ismail;Bahig M. Atia;Mohammed S. Alqahtani;K.A. Mahmoud
    • Nuclear Engineering and Technology
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    • v.55 no.1
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    • pp.278-284
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    • 2023
  • The synthetic B2O3-As2O3 glass ceramic are prepared to investigate the physical properties and the radiation shielding capabilities with the variation of concentration of the As2O3 with 10, 20, 30, and 40%, respectively. XRD analyses are performed on the fabricated glass-ceramic and depicted the improvement of crystallinity by adding As2O3. The radiation shielding properties are studied for the B2O3-As2O3 glass ceramic. The values of linear attenuation coefficient (LAC) are varied with the variation of incident photon gamma energy (23.1-103 keV). The LAC values enhanced from 12.19 cm-1-37.75 cm-1 by raising the As2O3 concentration from 10 to 40 mol% at low gamma energy (23.1 keV) for BAs10 and BAs40, respectively. Among the shielding parameters, the half-value layer, transmission factor, and radiation protection efficiency are estimated. Furthermore, the fabricated samples of glass ceramic have low manufacturing costs and good shielding features compared to the previous work. It can be concluded the B2O3-As2O3 glass ceramic is appropriate to apply in X-ray or low-energy gamma-ray shielding applications.

New skeletal dose coefficients of the ICRP-110 reference phantoms for idealized external fields to photons and neutrons using dose response functions (DRFs)

  • Bangho Shin;Yumi Lee;Ji Won Choi;Soo Min Lee;Hyun Joon Choi;Yeon Soo Yeom
    • Nuclear Engineering and Technology
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    • v.55 no.6
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    • pp.1949-1958
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    • 2023
  • The International Commission on Radiological Protection (ICRP) Publication 116 was released to provide a comprehensive dataset of the dose coefficients (DCs) for external exposures produced with the adult reference voxel phantoms of ICRP Publication 110. Although an advanced skeletal dosimetry method for photons and neutrons using fluence-to-dose response functions (DRFs) was introduced in ICRP Publication 116, the ICRP-116 skeletal DCs were calculated by using the simple method conventionally used (i.e., doses to red bone marrow and endosteum approximated by doses to spongiosa and/or medullary cavities). In the present study, the photon and neutron DRFs were used to produce skeletal DCs of the ICRP-110 reference phantoms, which were then compared with the ICRP-116 DCs. For photons, there were significant differences by up to ~2.8 times especially at energies <0.3 MeV. For neutrons, the differences were generally small over the entire energy region (mostly <20%). The general impact of the DRF-based skeletal DCs on the effective dose calculations was negligibly small, supporting the validity of the ICRP-116 effective DCs despite their skeletal DCs derived from the simple method. Meanwhile, we believe that the DRF-based skeletal DCs could be beneficial in better estimates of skeletal doses of individuals for risk assessments.

TET2DICOM-GUI: Graphical User Interface Based TET2DICOM Program to Convert Tetrahedral-Mesh-Phantom to DICOM-RT Dataset

  • Se Hyung Lee;Bo-Wi Cheon;Chul Hee Min;Haegin Han;Chan Hyeong Kim;Min Cheol Han;Seonghoon Kim
    • Progress in Medical Physics
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    • v.33 no.4
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    • pp.172-179
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    • 2022
  • Recently, tetrahedral phantoms have been newly adopted as international standard mesh-type reference computational phantoms (MRCPs) by the International Commission on Radiological Protection, and a program has been developed to convert them to computational tomography images and DICOM-RT structure files for application of radiotherapy. Through this program, the use of the tetrahedral standard phantom has become available in clinical practice, but utilization has been difficult due to various library dependencies requiring a lot of time and effort for installation. To overcome this limitation, in this study a newly developed TET2DICOM-GUI, a TET2DICOM program based on a graphical user interface (GUI), was programmed using only the MATLAB language so that it can be used without additional library installation and configuration. The program runs in the same order as TET2DICOM and has been optimized to run on a personal computer in a GUI environment. A tetrahedron-based male international standard human phantom, MRCP-AM, was used to evaluate TET2DICOM-GUI. Conversion into a DICOM-RT dataset applicable in clinical practice in about one hour with a personal computer as a basis was confirmed. Also, the generated DICOM-RT dataset was confirmed to be effectively implemented in the radiotherapy planning system. The program developed in this study is expected to replace actual patient data in future studies.