scholarly journals Optimasi Faktor Eksposi pada Pemeriksaan Radiografi Thorax menggunakan Computed Radiography

2020 ◽  
Vol 6 (1) ◽  
pp. 52-56
Author(s):  
Sri Sugiarti ◽  
Surip Surip ◽  
Merrytiana Fadila
Keyword(s):  
Radiation Dose ◽  
Nuclear Power ◽  
Radiation Safety ◽  
Computed Radiography ◽  
Reference Level ◽  
Radiographic Examination ◽  
Exposure Level ◽  
Exposure Factor ◽  
Chest Examination ◽  
Correlational Method

Concerning radiation safety must meet several radiation protection requirements which include justification or utilization of nuclear power, dose limitation, optimization of protection, and radiation safety. The purpose of this study was to determine the optimization of the exposure factor selection and determine the radiation dose received by the patient based on the selection of exposure factors on the thorax examination. The author observed the use of exposure factors on chest radiographic examination with a sample of 60 people. The design of this study uses the correlational method. The independent variables in this study are age, body weight, object thickness, kV, and mAs. Dependent variable exposure to radiation dose on chest examination. The conclusion of this study is the dose exposure level is influenced by age, object thickness, weight, and use of exposure factors which will then be obtained by the DRL (Diagnostic Reference Level) value.

scholarly journals Optimizing Analysis Of The Radiographic Image And Entrance Surface Dose Using Computed Radiography In Chest Examination

2018 ◽  
Vol 9 (2) ◽  
pp. 93-104
Author(s):  
Nursama Heru Apriantoro ◽  
Budi Santoso ◽  
Purwantiningsih Purwantiningsih ◽  
Tri Ambarsari
Keyword(s):  
Standard Deviation ◽  
Radiation Dose ◽  
Dose Level ◽  
Computed Radiography ◽  
Image Noise ◽  
Surface Dose ◽  
Variation Analysis ◽  
Radiographic Image ◽  
Exposure Factor ◽  
Chest Examination

This research has conducted about exposure factor variation analysis examination of the thorax surface dose and image noise in radiography. Do 10 (ten) times the exposure in the thorax phantom with various exposure factor such as 50 kV- 8 mAs, 50 kV-10 mAs, 55 kV- 8 mAs, 55 kV-10 mAs, 55 kV-10 mAs, 60 kV- 8 mAs, 60 kV-10 mAs, 66 kV-8 mAs, 66 kV-10 mAs, and 102 kV- 1 mAs, 102 kV - 2,5 mAs for high kV technique. For each exposure factor the pinned , TLD placed in the middle of the field to measure the radiation dose level. The optimum exposure conditions of the thorax PA examination (expressed with IgM value) occurs when using exposure factor 55 kV and 8 mAs for IgM values ​​obtained are 1.91, 6.605 for standard deviation values ​​and ESD 0.098 mGy.

scholarly journals Standarisasi Indeks Eksposur untuk Memenuhi Kriteria Anatomi dan Aspek Teknis pada Radiografi Thorax Pediatrik

2021 ◽  
Vol 7 (1) ◽  
pp. 22-27
Author(s):  
Mukhammad Lutfan Nurrokhim ◽  
Dwi Rochmayanti ◽  
Ari Budiono
Keyword(s):  
Computed Radiography ◽  
Descriptive Analysis ◽  
Technical Aspect ◽  
Radiographic Examination ◽  
Exposure Index ◽  
Exposure Factor ◽  
Pediatric Chest ◽  
Chest Examination ◽  
Index Value ◽  
The Right

Background: Computed Radiography has an exposure index that used as an exposure indicator. But on radiographic examination, exposure index value  sometimes ignored, and in  the preliminary survey of pediatric chest examination resulting a large exposure index range. The aim of this study is to know the profile of exposure index value and the setting of the exposure factors, the assessment of anatomy criteria and technical aspect, and the right exposure factors such as kV and mAs on pediatric chest examination.Methods: The type of this research is descriptive quantitative. The research was done by collecting data related to pediatric chest radiograph (≤ 2 years) the value of exposure index was recorded, then the radiograph was assessed using questionnaires that filled by one respondent who is a radiologist. The data was analyzed by displaying the data of exposure index and anatomy criteria from questionnaires into the table form, and then conducted a descriptive analysis to be drawn conclusions.Results: The results showed the profile of exposure index value and the setting of the exposure factor  has a fairly large exposure index range of 1084 – 2175, using 40 kV and 10 mAs and the collimation still often exceeds the object. Then for the assessment of the thorax anatomical criteria and the technical aspect overall was “Good Enough”, and the right exposure factors, that is: at 6 and 7 cm chest thickness was using 60 kV and 1,6 mAs; at 11 cm chest thickness was using 60 kV and 2 mAs, FFD 100 cm, and the setting of collimation as wide as object, the exposure index generated in the normal range that is 1251 – 1382.Conclusion: The right exposure factors on pediatric chest examination, that is: at 6 and 7 cm chest thickness was using 60 kV and 1,6 mAs; at 11 cm chest thickness was using 60 kV and 2 mAs, FFD 100 cm, and the setting of collimation as wide as object. 

scholarly journals SOCIALIZATION OF RADIOGRAPHER UNDERSTANDING OF DIAGNOSTIC REFERENCE LEVEL AS AN EFFORT TO OPTIMIZE RADIOGRAPHIC EXAMINATION

2021 ◽  
Vol 8 (1) ◽  
pp. 1-10
Author(s):  
Muhammad Irsal ◽  
Mayarani ◽  
Bambang Suroso ◽  
Muhammad Ichsan ◽  
Andri Yansyah
Keyword(s):  
Radiation Dose ◽  
Quantitative Description ◽  
Reference Level ◽  
Radiographic Examination ◽  
X Rays ◽  
Diagnostic Reference Level ◽  
Radiation Dose Rate ◽  
Test Number ◽  
Radiation Output ◽  
Post Test

The use of X-rays cannot be separated from the radiation given to the patient's body, therefore the radiation exposure received by patients should be very low according to the ALARA principle (As Low As Reasonably Achieveable). The research method is a quantitative description by using themeasurement method radiation output as a reference for the estimated radiation dose received by the patient, then the analysis of the success of socialization to radiographers about DRL as an optimization effort in radiographic examination. The results of the radiation dose estimation using themethod radiation output by determining theequation power function of themeasurement radiation output where the value of the radiation dose rate increases as the kVp value increases with y= 0.0005x2.9242. From theresults, it was pre-test found that the number of correct answers was 120 and 84 wrong, with a percentage of 59% and the number of respondents 10.03 people. Meanwhile, for theresults, the post-test number of correct answers was 194 and 12 wrong, with a percentage of 94% and the number of respondents being 15.98 people. It is hoped that radiographers can apply the principle of optimization in carrying out all radiographic examinations.

Radiocesium contamination in wild mouse in Fukushima, Japan

2021 ◽  
Author(s):  
Hiroko Ishiniwa ◽  
Masanori Tamaoki ◽  
Daiji Endoh ◽  
Manabu Onuma
Keyword(s):  
Radiation Dose ◽  
Nuclear Power ◽  
Wild Mouse ◽  
Current Status ◽  
Reference Level ◽  
Field Mouse ◽  
Apodemus Speciosus ◽  
Wild Mice ◽  
Japanese Forest ◽  
Electron Photon

<div><span>The large Japanese field mouse (<em>Apodemus speciosus</em>) which endemic wild mice living in Japanese forest, was monitored after the Fukushima nuclear power plant released a large amount of radioactive materials due to accident. We will introduce current status of radiocesium contamination, estimated radiation dose, and effect in the field mouse. According to calculation of radiation dose using Monte Carlo electron-photon transport code EGS5, it was clarified that dose rate level of the field mouse fall under derived consideration reference level determined by ICRP. Analysis of the oxidative stress in male mice testis revealed the damage in testicular cells of mice collected in 2012, when monitoring began.</span></div>

scholarly journals Assessment of the Local Exposure Level during Adult Chest X-Rays at the Ngaoundere Regional Hospital, Cameroon

2019 ◽  
Vol 2019 ◽  
pp. 1-5
Author(s):  
Guiswe Gnowe ◽  
Henri Paul Ekobena Fouda ◽  
Mbo Amvene Jéremie ◽  
Takmou Pascal ◽  
Bonaventure Babinne Graobe
Keyword(s):  
Adult Patients ◽  
Reference Level ◽  
Skin Dose ◽  
Exposure Level ◽  
X Rays ◽  
Entrance Skin Dose ◽  
Chest Examination ◽  
Local Exposure ◽  
Skin Doses

Background. The purpose of this study was to estimate the doses delivered to adult patients during chest examination for comparison with those elsewhere and to establish a local diagnostic reference level for the chest. The doses delivered in the standard X-ray examinations are not sufficiently optimized and controlled. The working protocols for the same exam given differ for similar morphotypes within the same hospital structure. Materials and Methods. The entrance skin dose (mGy) of the chest was evaluated on 105 adult patients with a mass of 70 ± 10 kg in accordance with the 75th percentile of the irradiation parameters. The analysis and processing of the data was carried out by Excel 2010. The entrance skin dose of the chest obtained in mGy was 0.18 ± 0.21 for the PA incidence. Conclusion. The present study allowed us to observe large variations at the entrance skin doses of the chest. These variations have made it possible to understand that the entrance skin doses to the chest are optimized and do not exceed the proportions of those estimated by others and standards internationally. This aspect demonstrates that the diagnostic reference levels as enumerated are dependent on the doses delivered and include not only the notions of quality of the radiographic image and the quality assurance of the radiological equipments but also the level of the manipulators trained.

scholarly journals Radiation Dose Calculations for a Hypothetical Accident in Xianning Nuclear Power Plant

2016 ◽  
Vol 2016 ◽  
pp. 1-6 ◽  
Author(s):  
Bo Cao ◽  
Junxiao Zheng ◽  
Yixue Chen
Keyword(s):  
Radiation Dose ◽  
Nuclear Power ◽  
Atmospheric Dispersion ◽  
Harmful Effect ◽  
Atmospheric Stability ◽  
Dispersion Modeling ◽  
Dose Calculations ◽  
Air Concentration ◽  
The Public ◽  
Ground Deposition

Atmospheric dispersion modeling and radiation dose calculations have been performed for a hypothetical AP1000 SGTR accident by HotSpot code 3.03. TEDE, the respiratory time-integrated air concentration, and the ground deposition are calculated for various atmospheric stability classes, Pasquill stability categories A–F with site-specific averaged meteorological conditions. The results indicate that the maximum plume centerline ground deposition value of1.2E+2 kBq/m2occurred at about 1.4 km and the maximum TEDE value of1.41E-05 Sv occurred at 1.4 km from the reactor. It is still far below the annual regulatory limits of 1 mSv for the public as set in IAEA Safety Report Series number 115. The released radionuclides might be transported to long distances but will not have any harmful effect on the public.

Justification of Remediation Criteria of Uranium Legacy Sites

2021 ◽  
Vol 66 (4) ◽  
pp. 54-57
Author(s):  
A. Titov ◽  
N. Shandala ◽  
Yu. Bel'skih ◽  
D. Isaev ◽  
M. Semenova ◽  
...  
Keyword(s):  
Effective Dose ◽  
Radiation Safety ◽  
Annual Effective Dose ◽  
Uranium Mining ◽  
Radioactive Material ◽  
Reference Level ◽  
Federal Law ◽  
Reference Levels ◽  
Economic Activities ◽  
Safety Standards

Purpose: To present approaches to establishing the criteria for remediation of sites contaminated due to past activities of uranium mining and milling facilities. These facilities are considered today as uranium legacy. Results: This paper presents the justified reference levels expressed in terms of annual effective dose values, which are recommended for using as remediation criteria for sites contaminated due to past activities of uranium mining and milling facilities (uranium legacy sites). Depending on further use of the sites after remediation, these criteria range from 1 µSv/year, in case of temporary presence of the population, to 10 µSv/year, in case of permanent residence of the population and conducting economic activities. Conclusions: In accordance with the international basic safety standards, accepted more than 10 years ago, exposure situations from radioactive material retained from previous activities refer to the existing exposure situation. Nevertheless, neither Federal Law “On Radiation Safety of the Population” nor Radiation Safety Standards have so far introduced terms “existing exposure situation” covering exposure at nuclear and uranium legacy sites and “reference level”, which is used to assure radiation safety of the population living at legacy sites or using these sites for the purpose of the economic activities.

Radiation Dose Evaluation of Typical Design Basis Accident for Advanced PWR in China

2021 ◽  
Author(s):  
Haiying Chen ◽  
Shaowei Wang ◽  
Xinlu Tian ◽  
Fudong Liu
Keyword(s):  
Radiation Dose ◽  
Effective Dose ◽  
Half Life ◽  
Nuclear Power ◽  
Outer Boundary ◽  
Design Basis ◽  
Loss Of Coolant Accident ◽  
Design Basis Accident ◽  
Typical Design ◽  
Total Effective Dose

Abstract The loss of coolant accident (LOCA) is one of the typical design basis accidents for nuclear power plant. Radionuclides leak to the environment and cause harm to the public in LOCA. Accurate evaluation of radioactivity and radiation dose in accident is crucial. The radioactivity and radiation dose model in LOCA were established, and used to analyze the radiological consequence at exclusion area boundary (EAB) and the outer boundary of low population zone (LPZ) for Hualong 1. The results indicated that the long half-life nuclides, such as 131I, 133I, 135I, 85Kr, 131mXe, 133mXe and 133Xe, released to environment continuously, while the short half-life nuclides, such as 132I, 134I, 83mKr, 85mKr, 87Kr, 88Kr, 135mXe and 138Xe, no longer released to environment after a few hours in LOCA. 133Xe may release the largest radioactivity to environment, more than 1015Bq. Inhalation dose was the major contribution to the total effective dose. The total effective dose and thyroid dose of Hualong 1 at EAB and the outer boundary of LPZ fully met the requirements of Chinese GB6249.

Study on Radiation Dose Calculation of PWR Spent Fuel Storage and Transportation

2021 ◽  
Author(s):  
Wen Yang ◽  
Xing Li ◽  
Jinrong Qiu ◽  
Lun Zhou
Keyword(s):  
Radiation Dose ◽  
Normal Condition ◽  
Radiation Safety ◽  
Spent Fuel ◽  
Dose Rates ◽  
Storage Pool ◽  
Transport Container ◽  
Photon Dose ◽  
Spent Fuel Storage ◽  
Fuel Storage

Abstract With the rapid development of nuclear energy, spent fuel will accumulate in large quantities. Spent fuel is generally cooled and placed in a storage pool, and then transported to a reprocessing plant at an appropriate time. Because spent fuel is content with a high level of radiation, spent fuel storage and transportation safety play important roles in the nuclear safety. Radiation dose safety are checked and validated using source analysis and Monte Carlo method to establish a radiation dose rate calculation model for PWR spent fuel storage pool and transport container. The calculation results show that the neutron and photon dose rates decrease exponentially with increase of water level under normal condition of storage pool. The attenuation multiples of neutron and photon dose rates are 4.64 and 1.59, respectively. According to radiation dose levels in different water height situations, spent fuel pool under loss of coolant accident can be divides into five workplaces. They are supervision zone, regular zone, intermittent zone, restricted zone and radiation zone. Under normal condition of transport container, the dose rates at the surface of the container and at a distance of 1 m from the surface are 0.1759 mSv/h and 0.0732 mSv/h, respectively. The dose rates decrease with the increasing radius of break accident, and dose rate at the surface of the transport container is 0.278 mSv/h when the break radius is 20 cm. Transport container conforms to the radiation safety standards of International Atomic Energy Agency (IAEA). This study can provide some reference for radiation safety analysis of spent fuel storage and transportation.

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