• Title/Summary/Keyword: Background Radiation

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Daylight background radiation modeling for the system of ocean-atmosphere with multi-layer clouds

  • Sushkevich, Tamara A.;Strelkov, Sergey A.;Volkovich, Alexander N.;Kulikov, Alexey K.;Maksakova, Sveta V.
    • Proceedings of the KSRS Conference
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    • v.2
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    • pp.680-683
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    • 2006
  • A one-dimensional planar model is considered of the atmosphere with multi-layer clouds illuminated by a mono-directional parallel flux of solar radiation. A new approach is proposed to radiation transfer modeling and daylight background formation for the atmosphere with such clouds that is represented as a heterogeneous multi-layer system each layer of which is described by different optical characteristics. The influence functions of each layer are determined by solutions of the radiation transfer boundary problem with an external monodirectional wide flux while the contribution of multiple scattering and absorption in the layer is taking into account.

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Quality Control of Radiation Counting Systems and Measurement of Minimum Delectable Activity (방사선 계측기의 품질관리 및 최소검출방사능 측정)

  • 송병철;한성심;김영복;지광용;손세철
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2004.06a
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    • pp.419-424
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    • 2004
  • Various radiation counters have been using to determine radioactivity of radwastes for disposal. A radiation counting system was set up using a radiation detector chosen in this study and its stability was investigated through the periodic determination of background and counting efficiencies in accordance with a quality control program to increase the confidence level. The average background level for the $\gamma$-spectrometer was 1.59 cps and the average counting level for the standard sample was 45248 Ops within $2{\sigma}$ confidence levels. The average alpha background level for the low background ${\alpha}{\beta}$ counting system was 0.31 cpm and the efficiency for alpha counting was 34.38%. The average beta background level for the ${\alpha}{\beta}$ counting system was 1,30 cpm and the efficiency for beta counting was 46.5%, The background level in the region of 3H and 14C for the liquid scintillation counting system was 2.52 and 3.31 cpm and the efficiency for alpha counting was 58.5 and 95.6%, respectively. The minimum detectable activity for the$\gamma$-spectrometer was found to be 3.2 Bq/$m\ell$ and 3.8 Bq/$m\ell$ for the liquid scintillation counter, and 20.5 and 23.0 Bq/$m\ell$, respectively for the $\alpha$ and $\beta$ counting system.

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TWO POSSIBLE COSMIC X-RAY SPECTRAL LINES

  • WU XUEJUN;Xu CHONGMING
    • Journal of The Korean Astronomical Society
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    • v.29 no.spc1
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    • pp.41-42
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    • 1996
  • A possible cosmic X-ray background(XRB) radiation related to original antimatter is considered. If the universe is made of separating domains of antimatter and matter, the photons produced by the annihilation of electron-positron and proton-antiproton on the last scattering surface would reach us in the energy $\~$0.45 keV and $\~$60 keV respectively because of the redshift. The spectrums of X-ray radiation from annihilation are deduced and a possible observational figure is described also.

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The System of Radiation Dose Assessment and Dose Conversion Coefficients in the ICRP and FGR

  • Kim, Sora;Min, Byung-Il;Park, Kihyun;Yang, Byung-Mo;Suh, Kyung-Suk
    • Journal of Radiation Protection and Research
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    • v.41 no.4
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    • pp.424-435
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    • 2016
  • Background: The International Commission on Radiological Protection (ICRP) recommendations and the Federal Guidance Report (FGR) published by the U.S. Environmental Protection Agency (EPA) have been widely applied worldwide in the fields of radiation protection and dose assessment. The dose conversion coefficients of the ICRP and FGR are widely used for assessing exposure doses. However, before the coefficients are used, the user must thoroughly understand the derivation process of the coefficients to ensure that they are used appropriately in the evaluation. Materials and Methods: The ICRP provides recommendations to regulatory and advisory agencies, mainly in the form of guidance on the fundamental principles on which appropriate radiological protection can be based. The FGR provides federal and state agencies with technical information to assist their implementation of radiation protection programs for the U.S. population. The system of radiation dose assessment and dose conversion coefficients in the ICRP and FGR is reviewed in this study. Results and Discussion: A thorough understanding of their background is essential for the proper use of dose conversion coefficients. The FGR dose assessment system was strongly influenced by the ICRP and the U.S. National Council on Radiation Protection and Measurements (NCRP), and is hence consistent with those recommendations. Moreover, the ICRP and FGR both used the scientific data reported by Biological Effects of Ionizing Radiation (BEIR) and United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) as their primary source of information. The difference between the ICRP and FGR lies in the fact that the ICRP utilized information regarding a population of diverse races, whereas the FGR utilized data on the American population, as its goal was to provide guidelines for radiological protection in the US. Conclusion: The contents of this study are expected to be utilized as basic research material in the areas of radiation protection and dose assessment.

Study on the safety management of radiation: centering on the radiation workers in medical institutions (방사선안전관리에 대한 조사 : 의료기관 방사선조사자를 중심으로)

  • 한은옥;문인옥
    • Korean Journal of Health Education and Promotion
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    • v.19 no.2
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    • pp.99-113
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    • 2002
  • While the use of radiation in the medical field provides diagnosis and treatment with important benefits, we cannot deny that the radiation bombing causes some hindrances. The expansion of radiation use in modem medicine is essential, so the radiation use and preparation of proper measure for safety management has risen as a pressing subject. Therefore, in order to make defensive plans for the prevention of health obstacles to general users of radiation and for the provision of basic data of the health education programs to radiation workers by grasping the knowledge, attitude and behavior towards the radiation safety management of radiation workers in each medical institution and by analyzing the factors that affect the actions of radiation safety management, in this study we conducted questionnaires from September 26 to November 5, 2001 targeting 805 radiation workers in 108 medical institutions including university hospitals, general hospitals, hospitals, clinics and public health centers etc. located in Seoul, four metropolitan cities and small and medium cities, and has obtained the following results. 1. The average point of knowledge on the radiation safety management was 10.96 out of 15. As for the general characteristics, the level of knowledge on radiation safety management was higher with older age, high education background and longer career. 2. The average point of attitude on the radiation safety management was 66.36 out of 75. The attitude point for general characteristics were higher with higher education background, longer career and in case of universities, the level of attitude on the radiation safety management was high. 3. The average of action points on the radiation safety management was 56.09 out of 75. In general characteristics, the action level of radiation safety level was higher with older age, longer career, and the reception of radiation education and in case of university hospitals. 4. It is analyzed that the relation of knowledge, attitude and behavior on the radiation safety management is higher as the levels of knowledge and attitude on the radiation safety management is higher. 5. As a result of analyzing the factors that affect the knowledge on the radiation safety management, the variables that can be explained best was in the order of ‘the behavior on the radiation safety management’, ‘work career’, ‘the attitude on the radiation safety management’, and ‘school career’. 6. As a result of analyzing the factors that affect the attitude on the radiation safety management, the variables that can be explained best was in the order of ‘the behavior on the radiation safety management’, ‘the knowledge on the radiation safety management’, and ‘school career’. 7. As a result of analyzing the factors that affect the behavior on the radiation safety management, the variables that can be explained best was in the order of ‘the attitude on the radiation safety management’, ‘the knowledge on the radiation safety management’, and ‘the frequency of radiation education

Assessment of Temporary Radioactivation for Tissue Expanders in Breast Radiation Therapy: Preliminary Study

  • Hwajung Lee;Do Hoon Oh;Lee Yoo;Minsoo Chun
    • Journal of Radiation Protection and Research
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    • v.48 no.2
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    • pp.100-106
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    • 2023
  • Background: As breast tissue expanders consist of metallic materials in the needle guard and ferromagnetic injection port, irradiation can produce radioactivation. Materials and Methods: A CPX4 (Mentor Worldwide LLD) breast tissue expander was exposed using the Versa HD (Elekta) linear accelerator. Two photon energies of 6 and 10 MV-flattening filter free (FFF) beams with 5,000 monitor units (MU) were irradiated to identify the types of radiation. Furthermore, 300 MU with 10 MV-FFF beam was exposed to the CPX4 breast tissue expander by varying the machine dose rates (MDRs) 600, 1,200, and 2,200 MU/min. To assess the instantaneous dose rates (IDRs) solely from the CPX4, a tissue expander was placed outside the treatment room after beam irradiation, and a portable radioisotope identification device was used to identify the types of radiation and measure IDR. Results and Discussion: After 5,000 MU delivery to the CPX4 breast tissue expander, the energy spectrum whose peak energy of 511 keV was found with 10 MV-FFF, while there was no resultant one with 6 MV-FFF. The time of each measurement was 1 minute, and the mean IDRs from the 10 MV-FFF were 0.407, 0.231, and 0.180 μSv/hr for the three successive measurements. Following 10 MV-FFF beam irradiation with 300 MU indicated around the background level from the first measurement regardless of MDRs. Conclusion: As each institute room entry time protocol varies according to the working hours and occupational doses, we suggest an addition of 1 minute from the institutes' own room entry time protocol in patients with CPX4 tissue expander and the case of radiotherapy vaults equipped with a maximum energy of 10 MV photon beams.

Relationship between Hospital Safety Symbol Shapes and Memory (병원 안전 심볼의 형태와 기억과의 관계)

  • Seok-Hwan Bae;Myung-Chul Park;Jae-Sang You;Yong-Gwon Kim;Cheul-Ho Ryoo;Dong-Hyun Oh
    • Journal of radiological science and technology
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    • v.46 no.2
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    • pp.115-122
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    • 2023
  • The purpose of this study was to examine the association between the shapes and colors of emergency exit symbols, magnetic field warning symbols, and radiation zone symbols used in hospitals for staff and patient safety and their effects on cognitive memory. The hippocampal region's signal intensity(SI) was analyzed using fMRI. The Symbol 2 (1.75±0.54) with a green background had the highest signal intensity (SI) for emergency exits, according to the findings. The black symbol 2 (1.60±0.51) with a yellow background had the highest signal intensity (SI) for the magnetic field warning symbol, followed by the black symbol 1 (1.59±0.65) with an orange background. The black symbol 2 (1.59±0.59) with a yellow background and the black symbol 3 (1.58±0.52) with an orange background had the low signal intensity with slight differences as for the radiation zone symbols. In conclusion, it was determined that the signal intensity of the black symbol with a yellow background was the highest in the magnetic field area and radiation area. This implies that symbols with a high signal intensity (SI) must be utilized intensively. To ensure that the correct meaning of the symbols is communicated in the future, they must also be utilized regularly and continually in disaster safety education.

THE EXTRACTION OF THE THERMAL RADIATION ASSOCIATED WITH GREENHOUSE GASES FROM AIRS MEASUREMENTS

  • Kwon, Eun-Han;Kim, Yong-Seung;Lee, Sun-Gu
    • Proceedings of the KSRS Conference
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    • v.1
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    • pp.301-304
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    • 2006
  • For the purpose of investigating the contributions of various gases to climate change, the thermal radiation associated with greenhouse gases are extracted from AIRS (Atmospheric Infrared Sounder) infrared radiances over the tropical pacific region. AIRS instrument which was launched on the EOS-Aqua satellite in May 2002 covers the spectral range from 650 cm-1 to 2700 cm-1 with a spectral resolution of between 0.4 cm-1 and 1 cm-1. In order to extract the thermal radiation absorbed by individual gases, the interfering background radiances at the top of the atmosphere are simulated using the radiative transfer code MODTRAN (MODerate spectral resolution atmospheric TRANsmittance). The simulations incorporated the temperature and water vapor profiles taken from NCEP (National Centers for Environmental Prediction) reanalyses. The differences between the simulated background radiance and AIRS-measured radiance result in the absorption of upward longwave radiation by atmospheric gases (i.e. greenhouse effect). The extracted absorption bands of individual gases will allow us to quantify the radiative forcing of individual greenhouse gases and thus those data will be useful for climate change studies and for the validation of radiative transfer codes used in general circulation models.

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Lifetime Risk Assessment of Lung Cancer Incidence for Nonsmokers in Japan Considering the Joint Effect of Radiation and Smoking Based on the Life Span Study of Atomic Bomb Survivors

  • Shimada, Kazumasa;Kai, Michiaki
    • Journal of Radiation Protection and Research
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    • v.46 no.3
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    • pp.83-97
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    • 2021
  • Background: The lifetime risk of lung cancer incidence due to radiation for nonsmokers is overestimated because of the use of the average cancer baseline risk among a mixed population, including smokers. In recent years, the generalized multiplicative (GM)-excess relative risk (ERR) model has been developed in the life span study of atomic bomb survivors to consider the joint effect of radiation and smoking. Based on this background, this paper discusses the issues of radiation risk assessment considering smoking in two parts. Materials and Methods: In Part 1, we proposed a simple method of estimating the baseline risk for nonsmokers using current smoking data. We performed sensitivity analysis on baseline risk estimation to discuss the birth cohort effects. In Part 2, we applied the GM-ERR model for Japanese smokers to calculate lifetime attributable risk (LAR). We also performed a sensitivity analysis using other ERR models (e.g., simple additive (SA)-ERR model). Results and Discussion: In Part 1, the lifetime baseline risk from mixed population including smokers to nonsmokers decreased by 54% (44%-60%) for males and 24% (18%-29%) for females. In Part 2, comparison of LAR between SA- and GM-ERR models showed that if the radiation dose was ≤200 mGy or less, the difference between these ERR models was within the standard deviation of LAR due to the uncertainty of smoking information. Conclusion: The use of mixed population for baseline risk assessment overestimates the risk for lung cancer due to low-dose radiation exposure in Japanese males.