• 제목/요약/키워드: He irradiation

검색결과 131건 처리시간 0.031초

생혈구분석을 통한 He-Ne laser 정맥혈관내 조사의 효과 (Effect of He-Ne laser intravascular irradiation by live blood analysis)

  • 공민준;안종석;유호룡;김용진;배경일;김윤식;설인찬
    • 대한한방내과학회지
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    • 제21권5호
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    • pp.705-713
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    • 2000
  • Objectives : The purpose of this study was to investigate the effect of Intravascular Laser Irradiation of Blood(ILlB) by the live blood analysis. Methods : We had analysed the changing forms of the live blood samples with Ultra Darkfield Microscope before and after Intravascular Laser Irradiation of Blood. Results : 1. Somatid did not showed significant change. 2. In the rouleau of red blood cells was decreased significantly. 3. In the morphological change of red blood cells, Burr cell, Ovalocyte and Poikilocyte were decreased significantly, but Acanthocyte and Target cell were increased significantly. 4. In the abnormal matters in plasma, the Cholesterol cristal did not showed significant change, but the Aggregation of platelet, Lipids, Spicule, Leucocyte, Uric acid cristal did showed a little significant decrease. Conclusion : These findings suggest that live blood analysis is useful to judge the effect of treatment and diagnosis in oriental medicine, and with the effect of Intravascular Laser Irradiation of Blood, it had showed significant effect on rouleau of red blood cells, morphological change of red blood cells and abnormal matters in plasma.

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FAST irradiations and initial post irradiation examinations - Part I

  • G. Beausoleil;L. Capriotti;B. Curnutt;R. Fielding;S. Hayes;D. Wachs
    • Nuclear Engineering and Technology
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    • 제54권11호
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    • pp.4084-4094
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    • 2022
  • The Advanced Fuels Campaign Fission Accelerated Steady-state Test (FAST) at Idaho National Laboratory (INL) completed its first irradiation cycle within the Advanced Test Reactor (ATR). The test focused on the irradiation of alloy fuel forms for use in sodium fast reactors. The first cycle of FAST testing was completed and four rodlets were removed for the initial post irradiation examination (PIE). The rodlet design and irradiation conditions were evaluated using Monte Carlo N-Particle (MCNP) for as-run power history and COMSOL for temperature analysis. These rodlets include a set of low burnups (~2.5 % fissions per initial metal atoms [%FIMA]), control rodlets, and a helium-bonded annular rodlet (4.7 %FIMA). Nondestructive PIE has been completed and includes visual inspection, neutron radiography and gamma scanning of the FAST capsules and rodlets. Radiography confirmed the integrity of the experiments, revealed that the annulus in the annular fuel was filled at a modest burnup (4.7 %FIMA), and indicated potential slumping of the cooler rodlets at lower burnup. Precision gamma scanning indicated mostly usual fission product behavior, except for cesium in the He-bonded annular fuel. Future destructive PIE will be necessary to fully interpret the effects of accelerated irradiation on U-Zr metallic fuel behavior.

TEM investigation of helium bubble evolution in tungsten and ZrC-strengthened tungsten at 800 and 1000℃ under 40keV He+ irradiation

  • I. Ipatova;G. Greaves;D. Terentyev;M.R. Gilbert;Y.-L. Chiu
    • Nuclear Engineering and Technology
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    • 제56권4호
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    • pp.1490-1500
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    • 2024
  • Helium-induced defect nucleation and accumulation in polycrystalline W and W0.5 wt%ZrC (W0.5ZrC) were studied in-situ using the transmission electron microscopy (TEM) combined with 40 keV He+ irradiation at 800 and 1000℃ at the maximum damage level of 1 dpa. Radiation-induced dislocation loops were not observed in the current study. W0.5ZrC was found to be less susceptible to irradiation damage in terms of helium bubble formation and growth, especially at lower temperature (800 ℃) when vacancies were less mobile. The ZrC particles present in the W matrix pin the forming helium bubbles via interaction between C atom and neighbouring W atom at vacancies. This reduces the capability of helium to trap a vacancy which is required to form the bubble core and, as a consequence, delays, the bubble nucleation. At 1000 ℃, significant bubble growth occurred in both materials and all the present bubbles transitioned from spherical to faceted shape, whereas at 800 ℃, the faceted helium bubble population was dominated in W.

Radiation damage in helium ion-irradiated reduced activation ferritic/martensitic steel

  • Xia, L.D.;Liu, W.B.;Liu, H.P.;Zhang, J.H.;Chen, H.;Yang, Z.G.;Zhang, C.
    • Nuclear Engineering and Technology
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    • 제50권1호
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    • pp.132-139
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    • 2018
  • Nanocrystalline reduced activation ferritic/martensitic (RAFM) steel samples were prepared using surface mechanical attrition treatment (SMAT). Un-SMATed and SMATed reduced activation ferritic/martensitic samples were irradiated by helium ions at $200^{\circ}C$ and $350^{\circ}C$ with 2 dpa and 8 dpa, respectively, to investigate the effects of grain boundaries (GBs) and temperature on the formation of He bubbles during irradiation. Experimental results show that He bubbles are preferentially trapped at GBs in all the irradiated samples. Bubble denuded zones are clearly observed near the GBs at $350^{\circ}C$, whereas the bubble denuded zones are not obvious in the samples irradiated at $200^{\circ}C$. The average bubble size increases and the bubble density decreases with an increasing irradiation temperature from $200^{\circ}C$ to $350^{\circ}C$. Both the average size and density of the bubbles increase with an increasing irradiation dose from 2 dpa to 8 dpa. Bubbles with smaller size and lower density were observed in the SMATed samples but not in the un-SMATed samples irradiated in the same conditions, which indicate that GBs play an important role during irradiation, and sink strength increases as grain size decreases.

Combined Effect of Radiation and $7{\beta}$-Hydroxycholeslerol on Human Cervical Cancer Cells in vitro

  • Chae, Sung-Wook;Kang, Kyoung-Ah;Lee, Kyoung-Hwa;Zhang, Rui;Jung, Myung-Sun;Hyun, Jin-Won
    • 한국환경성돌연변이발암원학회지
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    • 제25권3호
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    • pp.104-109
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    • 2005
  • [ $7{\beta}$ ]-Hydroxycholesterol (cholest-5-ene-3, 7-diol, $7{\beta}$-OHC) showed the cytotoxicity on human cervical carcinoma cells (HeLa), $10{\mu}M$ of 50% inhibitory concentration. We evaluated $7{\beta}$-OHC as the possibility of radiation sensitizer. The combination effect of $7{\beta}-OHC\;and\;{\gamma}$-irradiation was measured using colony forming assay and flow cytometer with propidium iodide and $DiOC_6$ stained cells, respectively. The combined treatment of $7{\beta}-OHC\;and\;{\gamma}$-irradiation did not show significant enhancing effects on HeLa cells.

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630nm LED 광원이 세포 증식에 미치는 효과 (Effects of 630nm LED light source to the cell proliferntion)

  • 김태곤;천민우;박용필;김성환;송창훈;김영수
    • 한국전기전자재료학회:학술대회논문집
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    • 한국전기전자재료학회 2006년도 추계학술대회 논문집 Vol.19
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    • pp.349-350
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    • 2006
  • In this module, RED Light Emitting Diode was employed to replace for Low level He-Ne laser for medical applications Each experiment was performed to irradiation group and non-irradiation group for both Dog bone marrow and Rat tissue cells. MTT assay method was chosen to verify the cell increase of two groups and the effect of irradiation on cell proliferation was examined by measuring 590nm transmittance of ELISA reader. As a result, the cell increase of 37% on Dog bone marrow, 23% on Rat tissue cells was verified m irradiation group as compared to non-irradiation group. The fact that specific wavelength irradiation has an effect on cell vitality and proliferation is known through this study.

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뇌경색(腦硬塞)에 대(對)한 He-Ne laser 정맥혈관내(靜脈血管內) 조사(照射)의 효과(效果) (Effect of He-Ne laser intravascular irradiation in treatment of cerebral infarction)

  • 박양춘;안탁원;김동희;김병탁
    • 혜화의학회지
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    • 제9권1호
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    • pp.387-397
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    • 2000
  • 연구배경(硏究背景): He-Ne laser 정맥혈관내(靜脈血管內) 조사(照射) (Intravascular Laser Irradiation of Blood : ILIB)가 말초(末梢) 및 뇌혈관순환장애(腦血管循環障碍), 뇌기능장애(腦機能障碍), 동맥경화(動脈硬化) 등의 예방(豫防)과 치료(治療) 목적(目的)으로 사용(使用)되고 있으나 이에 대한 한의학(韓醫學)에서의 연구(硏究)는 찾아보기 힘들다. 이에 저자(著者)는 발병(發病) 48시간(時間) 이내(以內)에 내원(來院)하여 뇌전산화단층촬영(腦電算化斷層撮影)으로 진단(診斷)된 초기(初期) 뇌경색(腦梗塞) 환자(患者)에서 ILIB의 효과(效果)를 평가(評價)하고자 본(本) 연구(硏究)를 시행(施行)하였다. 아울러 흰쥐의 국소(局所) 뇌허혈(腦虛血)에 미치는 영향(影響)을 측정(測定)하였다. 방법(方法) : 대상(對象) 환자(患者) 40명(名)을 UC-SHJGS(우황청심환(牛黃淸心丸)-성향정기산(星香正氣散))만을 투여(投與)한 대조군(對照群)과 UC-SHJGS 투여(投與)와 ILIB를 병용(倂用)한 치료군(治療群)으로 나누어 시행(施行)하였다. 대상환자(對象患者)는 모두 변증(辨證)과 무관(無關)하게 UC, SHJGS만을 투여(投與)하고 침치료(鍼治療)는 중풍칠처혈(中風七處穴)로 한정(限定)하였으며 5일간(日間)의 치료기간(治療期間) 동안 치료군(治療群)에서는 출력(出力) 1.8-2.5mW의 He-Ne laser를 1일(日) 1회(回) 50분(分) 동안 조사(照射)하였다. 동물실험(動物實驗)은 흰쥐를 대상(對象)으로 중대뇌동맥(中大腦動脈)을 결찰(結紮)하여 국소(局所) 뇌허혈(腦虛血)을 유발(誘發)하고 대조군(對照群)과 ILIB를 실시(實施)한 실험군(實驗群)으로 나누어 그 허혈면적(虛血面積)과 부종율(浮腫率)을 측정(測定)하였다. 결과(結果) : 1. 증상호전지수(症狀好轉指數)는 대조군(對照群)과 치료군(治療群) 사이에 유의(有意)한 차이(差異)가 없었다. 2. 치료전후(治療前後) 측정(測定)한 내경동맥(內頸動脈) siphon부(部)의 혈관반응성(血管反應性)은 대조군(對照群)과 치료군(治療群)에서 모두 유의성(有意性)있는 변화(變化)가 없었다. 3. 치료전후(治療前後) 측정(測定)한 요골동맥(橈骨動脈)의 혈관반응성(血管反應性)은 대조군(對照群)과 치료군(治療群)에서 모두 유의성(有意性) 있는 변화(變化)가 없었다. 4. 치료전후(治療前後) 측정(測定)한 PT, a-PTT은 대조군(對照群)과 치료군(治療群)에서 모두 유의성(有意性)있는 변화(變化)가 없었고, fibrinogen은 치료군(治療群)에서 치료전(治療前)보다 유의성(有意性) 있게 증가(增加)하였으나 평균값이 정상(正常) 범위(範圍)에서 벗어나지 않았다. 5. 국소(局所) 뇌허혈(腦虛血) 동물(動物) 실험(實驗)에서는 실험군(實驗群)에서 신경학적(神經學的) 결손(缺損), 허혈(虛血) 면적율(面積率), 부종율(浮腫率)이 유의성(有意性)있게 감소(減少)하였다 결론(結論) : 이상(以上)의 연구(硏究) 결과(結果) 뇌경한(腦硬寒)의 초기(初期) 치료(治療)에서 기존(旣存)의 한의학(韓醫學) 치료(治療)에 ILIB를 추가(追加)하는 것이 치료(治療) 효과(效果)를 증가(增加)시킨다는 증거(證據)는 없었으며 동물(動物) 실험(實驗)에서는 뇌경색(腦梗塞)의 치료(治療)에 응용(應用)할 수 있는 가능성(可能性)을 보여주고 있으나 그 효과(效果)와 적응증(適應症)을 구체적(具體的)으로 증명(證明)하기 위한 체계적(體系的)이고 다양(多樣)한 임상실험(臨床實驗)이 지적(持績)되어야할 것으로 생각된다.

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Coupled irradiation-thermal-mechanical analysis of the solid-state core in a heat pipe cooled reactor

  • Ma, Yugao;Liu, Jiusong;Yu, Hongxing;Tian, Changqing;Huang, Shanfang;Deng, Jian;Chai, Xiaoming;Liu, Yu;He, Xiaoqiang
    • Nuclear Engineering and Technology
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    • 제54권6호
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    • pp.2094-2106
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    • 2022
  • The solid-state core of a heat pipe cooled reactor operates at high temperatures over 1000 K with thermal and irradiation-induced expansion during burnup. The expansion changes the gap thickness between the solid components and the material properties, and may even cause the gap closure, which then significantly influences the thermal and mechanical characteristics of the reactor core. This study developed an irradiation behavior model for HPRTRAN, a heat pipe reactor system analysis code, to introduce the irradiation effects such as swelling and creep. The megawatt heat pipe reactor MegaPower was chosen as an application case. The coupled irradiation-thermal-mechanical model was developed to simulate the irradiation effects on the heat transfer and stresses of the whole reactor core. The results show that the irradiation deformation effect is significant, with the irradiation-induced strains up to 2.82% for fuel and 0.30% for monolith at the end of the reactor lifetime. The peak temperatures during the lifetime are 1027:3 K for the fuel and 956:2 K for monolith. The gap closure enhances the heat transfer but caused high stresses exceeding the yield strength in the monolith.

Theoretical studies on the stabilization and diffusion behaviors of helium impurities in 6H-SiC by DFT calculations

  • Obaid Obaidullah;RuiXuan Zhao;XiangCao Li;ChuBin Wan;TingTing Sui;Xin Ju
    • Nuclear Engineering and Technology
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    • 제55권8호
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    • pp.2879-2888
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    • 2023
  • In fusion environments, large scales of helium (He) atoms are produced by a radical transformation along with structural damage in structural materials, resulting in material swelling and degradation of physical properties. To understand its irradiation effects, this paper investigates the stability, electronic structure, energetics, charge density distribution, PDOS and TDOS, and diffusion processes of He impurities in 6HSiC materials. The formation energy indicates that a stable, favorable position for interstitial He is the HR site with the lowest energy of 2.40 eV. In terms of vacancy, the He atom initially prefers to substitute at pre-existing Si vacancy than C vacancy due to lower substitution energy. The minimum energy paths (MEPs) with migration energy barriers are also calculated for He impurity by interstitial and vacancy-mediated diffusion. Based on its calculated energy barriers, the most possible diffusion path includes the exchange of interstitial and vacancy sites with effective migration energies ranging from 0.101 eV to 1.0 eV. Our calculation provides a better understanding of the stabilization and diffusion behaviors of He impurities in 6H-SiC materials.