• 제목/요약/키워드: Gamma-ray protection

검색결과 175건 처리시간 0.021초

Protective effects of Betula platyphylla var. japonica extracts against the cellular damage induced by reactive oxygen species

  • Ji, Sang-Jin;Kim, Jeong-Hee
    • International Journal of Oral Biology
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    • 제34권1호
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    • pp.15-20
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    • 2009
  • In our present study, total methanol extracts prepared from B. platyphylla var. japonica showed a significant increase in cell proliferation upon the induction of oxidative stress by hydrogen peroxide or $\gamma$-ray irradiation. Total methanol extracts were fractionated into five separate preparations i.e. n-hexane, dichloromethane, ethylacetate, n-butanol and water fractions. Among these, the ethylacetate and butanol fractions of B. platyphylla var. japonica showed the highest protective effects against oxidative stress induced by hydrogen peroxide. These fractions also showed strong protective effects against $\gamma$-ray irradiation. When we evaluated the cytotoxicity of these fractions, the butanol fraction showed no effects in a colony formation assay. In addition, the butanol fraction showed a cell proliferation activation effect evidenced by significant increase in the colony formation of $\gamma$-ray irradiated cells. Both a radical scavenging activity and clonogenic activity assay suggested that the mechanism behind this protective effect against reactive oxygen species may be due to the radical scavenging and cell proliferation activity of B. platyphylla var. japonica extracts.

흡수선량지수결정(吸收線量指數決定)에 관한 실험적(實驗的) 연구(硏究) (Experimental Study on the Determination of Absorbed dose Index)

  • 전재식;노재식;노성기;하정우;유영수;이현덕
    • Journal of Radiation Protection and Research
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    • 제7권1호
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    • pp.34-48
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    • 1982
  • 본 연구의 일차적 목적은 방사선 방호를 위하여 임의지점(任意地點)의 주변 방사선량의 수준을 특성(特性)짓는 방법의 하나로 ICRU가 정의(定義)한 흡수선량지수를 실측(實測)하는데 있는 바 이를 위한 실험은 에비실험과 본 실험의 두 단계로 나누어 수행하였다. 예비단계의 실험에서는 30cm 지름의 polyethylene구(球)를 사용한 반면 본 실험에서는 인체조직등가물질(人體組織等價物質)의 구(球)를 제작하였으며 두 실험 모두 $^{137}Cs$$^{60}Co$ 감마선장(線場)과 TRIGA Mark-II 원자로의 열중성자(熱中性子) column의 중성자공장(中性子工場)에서 행하여졌다. 감마선 흡수선량측정에는 TCD-700 $(^{7}LiF)$ chip을, 중성자선량측정에는 Au 방사화박(放射化薄)과 함께 TLD chip도 사용하였는데 이 경우에는 감마선의 기여를 판별해 내기 위하여 TLD-600 $(^{6}LiF)$과 TLD-700을 동시에 사용하였다. 감마선 조사(照射)의 경우 구(球) phantom내(內) 흡수선량의 이론적 해석은 Burlin의 공동이론(空洞理論)에서 유도된 Erlich의 방법을 썼으며, 중성자 선량해석에는 fluence-KERMA 변환방법을 사용하였다. 이들 선량에 관하여서는 특히 자세히 설명하였다. 해석에 실험결과는 모두 통계적으로 처리 분석하였으며 특히 심부선량분포(深部線量分布)는 규격화(規格化)한 값을 사용하여 도표(圖表)로 나타내는 한편, 결론에서는 방사선방호용 지수량(指數量) 실측(實測)의 가능성과 난점(難點)을 설명하고 해결하여야 할 문제점들을 언급(言及)하였다.

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A comprehensive evaluation of Mg-Ni based alloys radiation shielding features for nuclear protection applications

  • M.I. Sayyed;K.A. Mahmoud;Faras Q. Mohammed;Kawa M. Kaky
    • Nuclear Engineering and Technology
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    • 제56권5호
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    • pp.1830-1835
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    • 2024
  • The current study aims to study the impacts of the substitution of magnesium with nickel concentrations on physical and γ-ray shielding capacity of magnesium alloys. The density of the magnesium alloys under study is varied from 3.677 g/cm3 to 5.652 g/cm3, with raising the nickel content from 26.7 wt% to 54.8 wt% and reducing the magnesium concentration from 72.6 wt% to 44.2 wt%, respectively. Additionally, the examination of the γ-ray shielding capacity using the Monte Carlo simulation code shows that the substitution of magnesium by nickel content in the magnesium alloys was associated with an enhancement in the γ-ray shielding capacity, where the linear attenuation coefficient for the studied alloys was enhanced by 53.22 %, 52.45 %, and 52.52 % at γ-ray energies of 0.662 MeV, 1.252 MeV, and 1.408 MeV, respectively, with raising the nickel concentration from 26.7 wt% to 54.8 wt%. Simultaneously, the half-value thickness for magnesium alloys was reduced from 2.47 cm to 1.62 cm (at gamma ray energy of 0.662 MeV), from 3.39 cm to 2.22 cm (at gamma ray energy of 1.252 MeV), and from 3.60 cm to 2.36 cm (at gamma ray energy of 1.408 MeV), raising the nickel concentration from 26.7 wt % to 54.8 wt%, respectively. The study shows that the substitution of magnesium for nickel greatly enhanced the radiation shielding capacity of the magnesium alloys.

Physical and γ-ray shielding properties of Vietnam's natural stones: An extensive experimental and theoretical study

  • Ta Van Thuong;O.L. Tashlykov;A.M. Shironina;I.P. Voronin;E.V. Kuvshinova;D.O. Pyltsova;E.I. Nazarov;K.A. Mahmoud
    • Nuclear Engineering and Technology
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    • 제56권5호
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    • pp.1932-1940
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    • 2024
  • The current work deals with investigation of the gamma ray shielding properties for various natural stones from Vietnam to be applied in the radiation shielding applications. The physical and chemical properties affecting the γ-ray shielding performance were examined. The MH-300A density meter was utilized to measure the density (ρ, g/cm3) of stone samples, as well as the chemical composition of Vietnamese natural stones was measured using the X-ray fluorescence analyzer (Olympus X-5000). The study shows that the increase in Fe + Ca concentrations within the stone samples increases their density (from 2.48 to 2.86 g/cm3) accompanied with a reduction in the porosity (Φ, %) (from 8.23 to 0.15%) and water absorption (K, %) (from 3.42 to 0.05%) factors. Additionally, the increase in Fe + Ca concentrations increases the linear attenuation coefficient (μ, cm-1) of the studied stones, where the Vietnamese marble stone (M 3.1) with the highest Fe + Ca concentration (65.97 wt%) has the highest linear attenuation coefficient which varied between 3.781 and 0.155 cm-1 with raising the gamma ray energy between 0.040 and 1.332 MeV.

극저준위 감마선 분광시스템의 백그라운드 저감화를 위한 중성자 차폐체 설계 (Design of Neutron Shielder for Reducing Background of Low Level Gamma Ray Spectrometer)

  • 김태욱;박종묵;박종길;신상운;전재식
    • Journal of Radiation Protection and Research
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    • 제26권2호
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    • pp.67-71
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    • 2001
  • 극저준위 방사능측정시스템의 백그라운드에 영향을 주는 중성자를 차폐하기 위한 차폐체를 설계하였다. 중성자 차폐방법은 고 밀도 폴리에틸렌을 이용하여 고속중성자를 감속한 후 $B_4C$를 이용하여 감속된 열중성자를 흡수하는 방법을 이용하였다. 몬테카를로 모사방법인 MCNP4B 코드를 이용하여 계산한 결과 고 밀도 폴리에틸렌의 두께가 10 cm 일 때 열중성자속이 최대가 되는 것으로 나타났으며 감속된 중성자의 흡수는 용제에 자연상태의 $B_4C$ 분말을 30 w% 섞을 경우 2 mm의 두께에서 94%의 중성자 흡수가 일어나는 것으로 나타났다. 또한 몬테카를로 모사를 통한 계산결과의 타당성 여부를 조사하기 위하여 중성자 차폐실험 장치를 제작하여 실험 결과와 비교하였으며, 비교 결과 실험값과 일치하는 것으로 나타났다.

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Preliminary Research of CZT Based PET System Development in KAERI

  • Jo, Woo Jin;Jeong, Manhee;Kim, Han Soo;Kim, Sang Yeol;Ha, Jang Ho
    • Journal of Radiation Protection and Research
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    • 제41권2호
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    • pp.81-86
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    • 2016
  • Background: For positron emission tomography (PET) application, cadmium zinc telluride (CZT) has been investigated by several institutes to replace detectors from a conventional system using photomultipliers or Silicon-photomultipliers (SiPMs). The spatial and energy resolution in using CZT can be superior to current scintillator-based state-of-the-art PET detectors. CZT has been under development for several years at the Korea Atomic Energy Research Institute (KAERI) to provide a high performance gamma ray detection, which needs a single crystallinity, a good uniformity, a high stopping power, and a wide band gap. Materials and Methods: Before applying our own grown CZT detectors in the prototype PET system, we investigated preliminary research with a developed discrete type data acquisition (DAQ) system for coincident events at 128 anode pixels and two common cathodes of two CZT detectors from Redlen. Each detector has a $19.4{\times}19.4{\times}6mm^3$ volume size with a 2.2 mm anode pixel pitch. Discrete amplifiers consist of a preamplifier with a gain of $8mV{\cdot}fC^{-1}$ and noise of 55 equivalent noise charge (ENC), a $CR-RC^4$ shaping amplifier with a $5{\mu}s$ peak time, and an analog-to-digital converter (ADC) driver. The DAQ system has 65 mega-sample per second flash ADC, a self and external trigger, and a USB 3.0 interface. Results and Discussion: Characteristics such as the current-to-voltage curve, energy resolution, and electron mobility life-time products for CZT detectors are investigated. In addition, preliminary results of gamma ray imaging using 511 keV of a $^{22}Na$ gamma ray source were obtained. Conclusion: In this study, the DAQ system with a CZT radiation sensor was successfully developed and a PET image was acquired by two sets of the developed DAQ system.

Radioprotective Effect of Extracts from Plants Indigenous to Korea

  • Kang Kyoung-Ah;Zhang Rui;Chae Sung-Wook;Piao Mei Jing;Shin Tae-Kyun;Lee Nam-Ho;Park Jae-Woo;Hyun Jin-Won
    • Journal of Radiation Protection and Research
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    • 제31권3호
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    • pp.115-122
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    • 2006
  • We have screened the cytoprotective effect on $\gamma$-ray radiation induced oxidative stress from eighteen Korean plant extracts. Querus salicina, Clerodendron trichotomum, Lamium amplexicaule, Lozoste lancifolia and Malus baccata were found to scavenge 1,1-diphenyl-2-picrylhydrazyl (DPPH) radical and intracellular reactive oxygen species (ROS). As a result, extracts of these plants reduced cell death of Chinese hamster lung fibroblast (V79-4) cells induced by $H_2O_2$ treatment. In addition, these extracts protected cell death of V79-4 cells damaged by $\gamma$-ray radiation. In addition, these extracts scavenged ROS generated by radiation. Taken together, the results suggest that Quercus salicina, Clerodendron trichotomum, Lamium amplexicaule, Lozoste lancifolia and Malus baccata protect V79-4 cells against oxidative damage by radiation through scavenging ROS.

경량 연자성 소재의 군 시설물 적용 시 방사선 차폐효과 분석 (Analysis of Radiation Shielding Effect of Soft Magnetic Material applied to Military Facility)

  • 이상규;이상민;최경준;이병학
    • 한국방사선학회논문지
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    • 제15권2호
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    • pp.191-199
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    • 2021
  • 본 연구의 목적은 경량 연자성 소재의 방사선 차폐 효과를 분석하여 군사시설에 대한 적용 가능성을 확인하는 것이다. 연자성 물질은 EMP 차폐에 효과적인 것으로 알려져 있다. 이 물질이 방사선 차폐에도 효과적이라면 군 방호에 효과적으로 적용이 가능할 것으로 예상된다. 이에 본 연구에서는 감마선 차폐 효과를 확인하기 위해 Cs-137 및 Co-60 선원을 사용하여 실험을 수행하였으며, 중성자 차폐 효과를 평가하기 위해 Monte Carlo N-Particle (MCNP) 모델링을 적용하였다. 그 결과 연자성 소재의 두께가 증가함에 따라 감마선과 중성자의 선형 감쇠 법칙에 의한 차폐성능이 향상됨을 확인할 수 있었다. 따라서 연자성 소재를 군사용 구조물 등에 적용할 경우에 방사선 차폐에 효과적이라는 것을 확인하였다.