• Title/Summary/Keyword: Radiation Shielding

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Accumulation of Chlorogenic Acid as a near UV-shielding Compound in Cauliflower Grown under Enhanced UV-B Radiation

  • Shibata, Hitoshi;Tanaka, Tomoyuki;Yonemura, Takeshi;Sawa, Yoshihiro;Ishikawa, Takahiro
    • Journal of Photoscience
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    • v.9 no.2
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    • pp.436-438
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    • 2002
  • Since solar radiation contains wavelength essential for photosynthesis accompanying with near-UV light, UV-B effects on biological parameters and acclimation mechanisms are influenced by photosynthetically active radiation (PAR). Therefore, to elucidate near-UV shielding mechanism in higher plants, we cultivated cauliflower under usual solar radiation and increased UV-B from fluorescent lamps, two- or three-fold excess over continuously estimated UV-B dose in PAR during daytime, using computer regulated systems. Increased UV-B radiation had little effect on growth expressed as fresh weigh and leaf area. Water soluble low molecular weight compounds showing absorption in near UV region were enhanced according to the irradiated UV-B dose. One of compounds in cauliflower leaves was identified as chlorogenic acid. This was found to have no near-UV photosenSitizerable activity and is known to have an ability to scavenge a wide species of active oxygen. Another pro-oxidant compound that generates superoxide anion radical under near-UV irradiation was not induced by increased UV-B during cultivation, and identified as lumazine, a degradation product from folic acid.

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The Relationship of the Filtration and the Side-scattered Dose in Verious Radiation Shielding Materials (방사선차폐물질(放射線遮蔽物質)에서 발생(發生)하는 측방산란선(側方散亂線)의 측정(測定))

  • Huh, Joon;Kim, Chang-Kyun
    • Journal of radiological science and technology
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    • v.7 no.1
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    • pp.35-40
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    • 1984
  • Side-direction scattered dose from various radiation shielding materials was measured at 50cm distance from the central beam of primary ray by used several kinds of added filters for a x-ray deep therapeutic installation, the obtained results were as follows : 1. Dose rate by tube voltage was more increased at heavy filtration than light filtration. 2. Scattered doses produced by constant tube voltage in all shielding materials were decreased at heavier filtration. 3. Scattered doses produced by constant shielding material in all tube voltages were decreased at heavier filtration.

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An extensive investigation on gamma ray shielding features of Pd/Ag-based alloys

  • Agar, O.;Sayyed, M.I.;Akman, F.;Tekin, H.O.;Kacal, M.R.
    • Nuclear Engineering and Technology
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    • v.51 no.3
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    • pp.853-859
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    • 2019
  • A comprehensive study of photon interaction features has been made for some alloys containing Pd and Ag content to evaluate its possible use as alternative gamma radiations shielding material. The mass attenuation coefficient (${\mu}/{\rho}$) of the present alloys was measured at various photon energies between 81 keV-1333 keV utilizing HPGe detector. The measured ${\mu}/{\rho}$ values were compared to those of theoretical and computational (MCNPX code) results. The results exhibited that the ${\mu}/{\rho}$ values of the studied alloys are in the same line with results of WinXCOM software and MCNPX code results at all energies. Moreover, Pd75/Ag25 alloy sample has the maximum radiation protection efficiency (about 53% at 81 keV) and lowest half value layer, which shows that Pd75/Ag25 has superior gamma radiation shielding performance among the other compared alloys.

Dose Customized Apron Micro Functional Design Using Convergence Shielding Sheet (융합 차폐시트를 이용한 선량 맞춤형 에이프런 마이크로 기능성 디자인)

  • Kim, Seon-Chil
    • Journal of the Korea Convergence Society
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    • v.12 no.11
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    • pp.119-126
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    • 2021
  • Radiation shielding clothing for medical institutions is used based on lead equivalent of 0.25 mmPb. However, this study intends to study the shielding suit that can guarantee the user's activity while considering the sensitivity of each part of the body. By manufacturing based on eco-friendly shielding material, it was attempted to solve the weight problem and environmental problem of existing lead aprons, and to present the same shielding performance as lead equivalent in thickness. The fabric of the produced shielding sheet was manufactured through a calendar process that adjusts the thickness of the shielding sheet from lead equivalent 0.12 mmPb to 0.32 mmPb. In addition, the usability evaluation of the manufactured shielding clothes was conducted for the subjects who were workers in medical institutions. As a result, the activity became easier and the weight was reduced by 0.26 kg. In the future, it is thought that it is necessary to improve the shielding suit design considering the activity.

Evaluating the Efficiency of the Device in Shielding Scattered Radiation during Treatment of Carcinoma of the Penis (음경암의 방사선치료 시 자체 제작한 Device의 산란선 차폐 효과에 대한 유용성 평가)

  • Gim, Yang-Soo;Lee, Sun-Young;Lim, Suk-Gun;Gwak, Geun-Tak;Pak, Ju-Gyeong;Lee, Seung-Hoon;Hwang, Ho-In;Cha, Seok-Yong
    • The Journal of Korean Society for Radiation Therapy
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    • v.21 no.1
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    • pp.9-15
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    • 2009
  • Purpose: We evaluated the device that was created for maintaining the patient's setup and protecting the testicles from scattered radiation during treatment of carcinoma of the penis. Materials and Methods: The phantom testicles were made of vaseline cotton gauze and the device consisted of 5 mm of acryl box and 4 mm of lead shielding. $3{\times}3\;cm^2$, $4{\times}4\;cm^2$, $5{\times}5\;cm^2$, $6{\times}6\;cm^2$, $7{\times}7\;cm^2$ field sizes were used for this study and measurement was made at 4, 5, 6, 7, 8, 10 cm from the lower edge of the field for 10 times with lead shielding and without the shielding respectively. 200 cGy was delivered using 6 MV photons. Results: The scatted radiation without lead shielding at 4, 5, 6, 7, 8, 10 cm from the lower edge of the field were 14.8-4.7 cGy with $3{\times}3\;cm^2$, 15.7-5.2 cGy with $4{\times}4\;cm^2$, 17.6-5.5 cGy with $5{\times}5\;cm^2$, 19.9-6.6 cGy with $6{\times}6\;cm^2$, 22.2-7.6 cGy with $7{\times}7\;cm^2$ and the measured dose without lead shielding were 7.1-2.6 cGy with $3{\times}3\;cm^2$, 8.9-3.6 cGy with $4{\times}4\;cm^2$, 12.3-4.8 cGy with $5{\times}5\;cm^2$, 14.6-5.0 cGy with $6{\times}6\;cm^2$ and 21.1~6.4 cGy with $7{\times}7\;cm^2$. As shown above, the scatted radiation decreased after using lead shielding. Depending of the range of field sizes, the resulting difference between without shielding values and with shielding values were: 7.8-1.1 cGy at 4 cm, 5.1-1.2 cGy at 5 cm, 3.8-1.1 cGy at 6 cm, 3.4-1.7 cGy at 7 cm, 2.8-1.7 cGy at 8 cm, 2.4-2.5 cGy at 9 cm and 2.1-1.8 cGy at 10 cm. In the situation as described above, the range in values depending on the distance was 7.8-1.1 cGy with $3{\times}3\;cm^2$, 6.9-1.6 cGy with $4{\times}4\;cm^2$, 5.3-0.8 cGy with $5{\times}5\;cm^2$, 5.3-1.5 cGy with $6{\times}6\;cm^2$ and 1.1-1.8 cGy with $7{\times}7\;cm^2$. Conclusion: Using the device we created to shield the testicles from scattered radiation during treatment of carcinoma of the penis, we have found that scattered radiation to the testicles is decreased by the phantom testicles, and by increasing the distance between the testicles and penis.

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The radiation shielding proficiency and hyperspectral-based spatial distribution of lateritic terrain mapping in Irikkur block, Kannur, Kerala

  • S. Arivazhagan;K.A. Naseer;K.A. Mahmoud;N.K. Libeesh;K.V. Arun Kumar;K.ChV. Naga Kumar;M.I. Sayyed;Mohammed S. Alqahtani;E. El Shiekh;Mayeen Uddin Khandaker
    • Nuclear Engineering and Technology
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    • v.55 no.9
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    • pp.3268-3276
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    • 2023
  • The practice of identifying the potential zones for mineral exploration in a speedy and low-cost method includes the use of satellite imagery analysis as a part of remote sensing techniques. It is challenging to explore the iron mineralization of a region through conventional methods which are a time-consuming process. The current study utilizes the Hyperion satellite imagery for mapping the iron mineralization and associated geological features in the Irikkur region, Kannur, Kerala. Along with the remote sensing results, the field study and laboratory-based analysis were conducted to retrieve the ground truth point and geochemical proportion to verify the iron ore mineralization. The MC simulation showed for shielding properties indicate an increase in the linear attenuation coefficient with raising the Fe2O3+SiO2 concentrations in the investigated rocks where it is varied at 0.662 MeV in the range 0.190 cm-1 - 0.222 cm-1 with rising the Fe2O3+SiO2 content from 57.86 wt% to 71.15 wt%. The analysis also revealed that when the γ-ray energy increased from 0.221 MeV to 2.506 MeV, sample 1 had the largest linear attenuation coefficient, ranging from 9.33 cm1 to 0.12 cm-1. Charnockite rocks were found to have exceptional shielding qualities, making them an excellent natural choice for radiation shielding applications.

A study on performance evaluation of Apron by shielding rate and uniformity (방사선방어용앞치마(Apron)의 차폐율과 균일성 측정을 통한 성능평가 연구)

  • Yoo, Se-Jong;Lim, Chang-seon;Sim, Kyu-ran
    • Journal of the Korea Safety Management & Science
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    • v.17 no.1
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    • pp.103-109
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    • 2015
  • In this study, we quantitatively analyzed the data by measuring the radiation shielding rate and uniformity in order to evaluate the performance of an Apron. In addition, storage conditions were also evaluated. The uniformity measurement was performed by evaluating the Apron DICOM images using a PACS program. The experiment was intended for 51 Aprons being used in three hospitals in the Daejeon area. The radiation shielding rate and uniformity were measured per lead equivalent for 0.25 mmPb, 0.35 mmPb, and 0.5 mmPb. As a result, the higher lead equivalents were, the greater differences in the non-uniformity between the top part and the bottom part became (p=0.020). In all hospitals, regarding the non-uniformity of four places in Aprons, all showed statistically significant differences (p<0.01). The average value of the transmitted radiation dose showed less difference (p=0.005) in the bottom right than in the upper right but was statistically significant. There have been no marks of manufacturing date or the date of purchase in the Apron.

Evaluation for Mechanical Properties of Compress Strength and Dry Density of Concrete at NPP (원전 시설용 콘크리트의 압축강도 및 건조밀도 특성 평가)

  • Lee, Young-Dae;Kim, Gyu-Yong;Shin, Kyoung-Su;Nam, Jeong-Soo;Lee, Tae-Gyu;Choe, Gyeong-Choel
    • Proceedings of the Korean Institute of Building Construction Conference
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    • 2011.11a
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    • pp.53-54
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    • 2011
  • The facilities producing the nuclear energy chosen for resolving the recent global energy problem have been increasingly constructed, and hence more frequent durability tests on radiation shielding concrete are required due to NPP(Nuclear Power Plant) life extension and increase of radioactive waste repositories. Bulk dry density is one of the critical factors ensuring the durability and performance of the radiation shielding concrete because the design of the radiation shielding reinforced concrete structures for NPPs is based on the bulk dry density of the concrete. Bulk density of unconsolidated shielding concrete can be calculated utilizing a test assuring to satisfy the bulk dry density, or existing credible data set. This study evaluated correlation between bulk density and bulk dry density of the concrete used for Korean NPPs (y=1.0913X-0.2458) and developed a correlation expression considering standard deviation of bulk dry density (y=1.0913X-0.3358).

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An Analysis Using Numerical Model of Composite Multi-Layer Insulation for SOFC (SOFC용 고온 적층 단열재의 해석적 고찰)

  • CHOI, CHONGGUN;HWANG, SEUNG-SIK;CHOI, GYU-HONG
    • Transactions of the Korean hydrogen and new energy society
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    • v.30 no.6
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    • pp.540-548
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    • 2019
  • This study was conducted to develop insulation for solid oxide fuel cell (SOFC). The developed insulation is based on the lamination technology and the radiation shielding technology of the satellite insulation. The insulation material is consisting of insulation material for conduction resistance, spacer, and radiation shielding material. The experimental apparatus consisting vacuum bell jar, pump, heater and temperature recording device has developed to verify the performance of the insulation. The experimental values were used as reference data for the modeling development. In this paper, heat transfer is assumed to be one- dimensional phenomena for the prediction of insulation performance and internal temperature distribution in high temperature region of SOFC. The developed model was used to compare the performance difference of insulation types according to composition materials. The analysis result shows that the insulation including spacer and radiation shielding has better heat insulation performance than other cases. In this study, the thickness reduction effect of about 20% was shown compared to the insulation including only conductive material. It is noted that the radiant shielding material should be carefully selected for durability, because SOFC insulation should be used for a long time at high temperature.

An investigation of the nuclear shielding effectiveness of some transparent glasses manufactured from natural quartz doped lead cations

  • Kassem, Said M.;Ahmed, G.S.M.;Rashad, A.M.;Salem, S.M.;Ebraheem, S.;Mostafa, A.G.
    • Nuclear Engineering and Technology
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    • v.53 no.6
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    • pp.2025-2037
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    • 2021
  • The influence of lead cations on natural quartz (QZ) from Egypt as a glass shielding material for the composition with nominal formula (10Na2O - (90 - x) QZ - xPbO (where x = 30, 35, 40, 45 and 50 mol %)) was examined. The studied samples are synthesized via the melt quenching method at 1050 ℃. The X-ray diffraction XRD patterns were confirmed the glass nature for studied samples. Moreover, the optical properties, and the transparency for all compositions were examined by UV-Vis spectroscopy. Also, the major elemental composition of the natural quartz were estimated via the X-ray fluorescence (XRF) technique. Further, the density and molar volume were determined. Furthermore, the nuclear shielding parameters such as, mass attenuation coefficient, effective atomic number, electronic density, the total atomic, and electronic cross sections as well as the mean free path, and the half value layer with different gamma ray energies (81 keV-1407 keV) were calculated. Besides, the results showed that the shielding behavior towards the gamma ray radiation for all glass samples was increased as the increment in PbO concentration in the glass system.