• Title/Summary/Keyword: fluence

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Ion Beam Modified ppolyimide: A Study of the Irradiation Effect

  • Lee, Y.S.;Lim, K.Y.;Chung, Y.D.;Lee, K.M.;Choi, B.S.;Whang, C.N.
    • Proceedings of the Korean Vacuum Society Conference
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    • 1998.02a
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    • pp.132-132
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    • 1998
  • Ion bombardment in the keV range is known to induce drastic chemical modifications in organic and inoranic molecular comppounds. A degrading effects in orgainc materials such as the release of ppolymer compponents and the chemistry of the iradiation pprocess have been observed. The work to be described was carried out in order to understand the irradiation effect better. The sampple(ppolyimide : Kappton ) Were irradiated by Ar+, Ne+, H+ ions and electrons (3 keV) to fluence ranging from ~1$\times$1015 to ~1$\times$1017 ions/$cm^2$ at room tempperature. The impplant was usually rastered over an area of a few $cm^2$ . These ion impplantation were carried out in an electron sppectrometer ESCA 5700 (ppHI Ltd) at a residual gas ppressure of ~5$\times$10-10 Torr. X-ray pphotoelectron sppectroscoppy(XppS) measurements were made using a monochromatized Al Ka(1486.6 eV) excitation source. The pphotoemitted electrons were detected by hemisppherical analyser with a ppass energy of 23.5 eV. Core-level binding energies were referenced to the Fermi level. To avoid the charging effect it was used the neutralizer. We studied the irradiation effects on ppolyimide with Ar+, Ne+, He+ ions and electrons by XppS which 추 pprovide detailed information concerning the bonding-induced changes.

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Irradiation Behavior of Reactor Pressure Vessel SA508 class 3 Steel Weld Metals (압력용기강재 SA508 class 3 용착금속의 조사거동)

  • Koh, Jin-Hyun;Park, Hyoung-Keun;Kim, Soo-Sung;Hwang, Yong-Hwa;Seo, Yun-Seok
    • Journal of Welding and Joining
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    • v.28 no.5
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    • pp.69-74
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    • 2010
  • Irradiation behavior of the reactor pressure vessel SA508 class 3 steel weld metals was examined by Charpy V Notch impact specimens. The specimens were exposed to a fluence of $2.8{\times}1019$ neutrons(n)/$cm^2$(E>1 MeV) at $288^{\circ}C$. The irradiation damage of weld metal was evaluated by comparison between unirradiated and irradiated specimens in terms of absorbed energy and lateral expansion. The specimens for neutron irradiation were welded by submerged arc welding process at a heat input of 3.2 kJ/mm which showed good toughness in terms of weld microstructure, absorbed energy and lateral expansion. The post-irradiation Charpy V notch 41J and 68J transition temperature elevation were $65^{\circ}C$ and $70^{\circ}C$, respectively. This elevation was accompanied by a 20% reduction in Charpy V notch upper shelf energy level. The lateral expansion at 0.9mm irradiated Charpy specimens showed temperature elevation of $65^{\circ}C$ and was greatly decreased due to radiation damage.

Effect of Harmonic Generation and Countermeasures (고조파발생에 따른 영향과 대책 연구)

  • Baek, Dong-Hyun
    • Fire Science and Engineering
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    • v.29 no.6
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    • pp.91-97
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    • 2015
  • Skyscrapers, large business buildings, and IT consumers use many appliances, and the electrical power stems can cause fires by overheating. This can result in damaged capacitors, lost data, rising ground potential, and communication obstacles from linear or nonlinear high frequency. To make sure of that we investigated 7 spots of a building, among which 6-spots were fair but the other one needed high frequency control. Spots 3, 6, and 7 needed diagnostic workup, and spots 2, 3, and 5 considered 5 high frequency currents. A phase is all of good but the high frequency current is greater than the standard level except for spot 1. As a result, a zigzag transformer or active filter needs to be installed, and the efficiency needs to be upgraded by investigating load unbalance factors and power factors.

Neutron Irradiation Effects on the Magnetic Properties in Fe87Zr7B6 Amorphous Alloy (비정질 Fe87Zr7B6 합금의 중성자 조사량에 따른 자기적 특성변화)

  • Kim, Kyeong-Sup;Kim, Hyo-Chol;Yu, Seong-Cho
    • Journal of the Korean Magnetics Society
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    • v.15 no.1
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    • pp.12-16
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    • 2005
  • The $Fe_{87}Zr_{7}B_{6}$ amorphous alloy after neutron irradiation are studied hysteresis loop and complex permeability measurements. The total integration fluence of fast neutrons is varied from $1.92{\times}10^{14}$ to $4.85{\times}10^{16}n_{f1}cm^{-2}$. After neutron irradiation, the imaginary part of complex permeability in low frequency region decreased due to the decrease of wall motion, but the permeability in high frequency region increased due to the enhancement of rotational magnetization. The measurement of hysteresis loop showed the increase of magnetic softness, related to rotational magnetization, but saturation magnetization was decreased in neutron irradiation sample.

Evaluation of Probabilistic Fracture Mechanics for Reactor Pressure Vessel under SBLOCA (소규모 냉각재 상실사고하의 원자로 압력용기에 대한 확률론적 파괴역학 평가)

  • Kim, Jong Wook;Lee, Gyu Mahn;Kim, Tae Wan
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.4 no.2
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    • pp.13-19
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    • 2008
  • In order to predict a remaining life of a plant, it is necessary to select the components that are critical to the plant life. The remaining life of those components shall be evaluated by considering the aging effect of materials used as well as numerous factors. However, when evaluating reliability of nuclear structural components, some problems are quite formidable because of lack of information such as operating history, material property change and uncertainty in damage models. Accordingly, if structural integrity and safety are evaluated by the deterministic fracture mechanics approach, it is expected that the results obtained are too conservative to perform a rational evaluation of plant life. The probabilistic fracture mechanics approaches are regarded as appropriate methods to rationally evaluate the plant life since they can consider various uncertainties such as sizes and shapes of cracks and degradation of material strength due to the aging effects. The objective of this study is to evaluate the structural integrity for a reactor pressure vessel under the small break loss of coolant accident by applying the deterministic and probabilistic fracture mechanics. The deterministic fracture mechanics analysis was performed using the three dimensional finite element model. The probabilistic integrity analysis was based on the Monte Carlo simulation. The selected random variables are the neutron fluence on the vessel inside surface, the content of copper, nickel, and phosphorus in the reactor pressure vessel material, and initial RTNDT.

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Photosynthetic Responses and Photoprotection in Korean Hot Pepper (Capsicum annuum L.) against High Light Stress (광 스트레스에 대한 고추 잎의 광합성 반응과 광 보호 메커니즘)

  • Lee, Hae-Youn;Park, Youn-Il;Kim, Chang-Gi;Hong, Young-Nam
    • Korean Journal of Environmental Agriculture
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    • v.25 no.2
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    • pp.109-117
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    • 2006
  • Photoinhibition and photoprotection of PSII in the leaves of hot pepper (Capsicum annuum L.) grown in Hoagland solution and Tap water were compared. Though changes in the rates of $O_2$ evolution as a function of photon fluence rate (PFR) were comparable, the rates of respiration in the dark was 3 times higher in the Hoagland solution grown leaves than in the Tap-water grown ones. Compared to Hoagland solution grown plane, PSIIs of Tap water grown pepper leaves were more susceptible to photoinhibitory light treatment. In order to inactivate functional PSII to the same extents, Hoagland solution grown plants required almost 2-fold high light $(1600{\mu}molm^{-2}s^-)$ treatment than those of Tap water $(900{\mu}molm^{-2}s^-)$. Interestingly, the remaining fraction of PSII in Hoagland grown pepper was able to survive under prolonged illumination in the presence of lincomycin, which probably means that the growth condition of plant seemed to have an effect on the recovery of PSII from light stress. When PSII was severly photoinactivated at a chilling temperature, recovery was observed only if the residual functional PSII were not inhibited with DCMU, Nigericin and MV during recovery. In conclusion, PSIIs grown in the Hoagland solution was more resistant to excess light than in the Tap water grown one and the recovery of PSII from photodamage was more efficient in Hoagland grown pepper leaves than Tap water grown one, which means that the increased dark respiration may play a important role in the protection of PSII from photoinhibition by helping repair photosynthetic proteins (in particular, the D1 protein of PSII) degraded by photoinhibition.

The Development of Gamma Energy Identifying Algorithm for Compact Radiation Sensors Using Stepwise Refinement Technique

  • Yoo, Hyunjun;Kim, Yewon;Kim, Hyunduk;Yi, Yun;Cho, Gyuseong
    • Journal of Radiation Protection and Research
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    • v.42 no.2
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    • pp.91-97
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    • 2017
  • Background: A gamma energy identifying algorithm using spectral decomposition combined with smoothing method was suggested to confirm the existence of the artificial radio isotopes. The algorithm is composed by original pattern recognition method and smoothing method to enhance the performance to identify gamma energy of radiation sensors that have low energy resolution. Materials and Methods: The gamma energy identifying algorithm for the compact radiation sensor is a three-step of refinement process. Firstly, the magnitude set is calculated by the original spectral decomposition. Secondly, the magnitude of modeling error in the magnitude set is reduced by the smoothing method. Thirdly, the expected gamma energy is finally decided based on the enhanced magnitude set as a result of the spectral decomposition with the smoothing method. The algorithm was optimized for the designed radiation sensor composed of a CsI (Tl) scintillator and a silicon pin diode. Results and Discussion: The two performance parameters used to estimate the algorithm are the accuracy of expected gamma energy and the number of repeated calculations. The original gamma energy was accurately identified with the single energy of gamma radiation by adapting this modeling error reduction method. Also the average error decreased by half with the multi energies of gamma radiation in comparison to the original spectral decomposition. In addition, the number of repeated calculations also decreased by half even in low fluence conditions under $10^4$ ($/0.09cm^2$ of the scintillator surface). Conclusion: Through the development of this algorithm, we have confirmed the possibility of developing a product that can identify artificial radionuclides nearby using inexpensive radiation sensors that are easy to use by the public. Therefore, it can contribute to reduce the anxiety of the public exposure by determining the presence of artificial radionuclides in the vicinity.

A Study on Transmuted Impurity Atoms Formed in Neutron-Irradiated ZnO Thin Films (중성자 조사한 ZnO 박막에 생성된 핵전환 불순물들에 대한 연구)

  • Kim, Sang-Sik;Seon, Gyu-Tae;Park, Gwang-Su;Im, Gi-Ju;Seong, Man-Yeong;Lee, Bu-Hyeong;Jo, Un-Gap;Han, Hyeon-Su
    • The Transactions of the Korean Institute of Electrical Engineers C
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    • v.51 no.7
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    • pp.298-304
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    • 2002
  • Transmuted impurity atoms formed in neutron-irradiated ZnO thin films were theoretically identified first and then experimentally confirmed by photoluminescence (PL). ZnO thin films grown by plasma-assisted molecular beam epitaxy were irradiated by neutron beam at room temperature. The ZnO films consist of eight constituent (Zn and O) isotropes, of which four are transmutable by neutron-irradiation; $^{64}$ , $^{68}$ Zn, $^{70}$ Zn and $^{18}$ O were expected to transmute into $^{65}$ Cu, $^{69}$ Ga, $^{71}$ Ga, and $^{19}$ F, respectively. The concentrations of these transmuted atoms were estimated in this study by considering natural abundance, neutron fluence and neutron cross section. The neutron-irradiated ZnO thin films were characterized by PL. In the PL spectra of the ZnO thin films, the Cu-related PL peaks were seen, but the Ga- or F-associated PL peaks were absent. This observation confirmed the existence of $^{65}$ Cu in the ZnO, but it could not do the formation of the other two. In this paper, the emission mechanism of Cu impurities is described and the reason for the absence of the Ga- or F-associated PL peaks is discussed as well.

Fabrication and Characterization of Ge/B-doped Optical Fiber for UV Poling Applications (UV 폴링용 Ge와 B가 첨가된 실리카 유리 광섬유 제조 및 특성 평가)

  • Kim, Bok-Hyeon;Ahn, Tae-Jun;Heo, Jong;Shin, Dong-Wook;Han, Won-Taek
    • Journal of the Korean Ceramic Society
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    • v.39 no.12
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    • pp.1158-1163
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    • 2002
  • An Ge/B-doped optical fiber with high photosensitivity was fabricated to induce large second-order optical nonlinearity by UV poling. It was found that long period fiber gratings were inscribed on the fiber by the 248 nm KrF excimer laser irradiation with pulse energy of 116 mJ/$cm^2$ and pulse frequency of 10 Hz without hydrogen loading treatment. The photosensitivity was measured by use of the long period fiber grating pair method and the refractive index change of 3.3$10{\times}^{-3}$ was found to be induced in the core of the optical fiber by the KrF excimer laser irradiation of 8.67 kJ/$cm^2$. An H-shaped optical fiber was also fabricated for the UV poling through optimization of the fiber drawing condition.

MECHANICAL AND IRRADIATION PROPERTIES OF ZIRCONIUM ALLOYS IRRADIATED IN HANARO

  • Kwon, Oh-Hyun;Eom, Kyong-Bo;Kim, Jae-Ik;Suh, Jung-Min;Jeon, Kyeong-Lak
    • Nuclear Engineering and Technology
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    • v.43 no.1
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    • pp.19-24
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    • 2011
  • These experimental studies are carried out to build a database for analyzing fuel performance in nuclear power plants. In particular, this study focuses on the mechanical and irradiation properties of three kinds of zirconium alloy (Alloy A, Alloy B and Alloy C) irradiated in the HANARO (High-flux Advanced Neutron Application Reactor), one of the leading multipurpose research reactors in the world. Yield strength and ultimate tensile strength were measured to determine the mechanical properties before and after irradiation, while irradiation growth was measured for the irradiation properties. The samples for irradiation testing are classified by texture. For the irradiation condition, all samples were wrapped into the capsule (07M-13N) and irradiated in the HANARO for about 100 days (E > 1.0 MeV, $1.1{\times}10^{21}\;n/cm^2$). These tests and results indicate that the mechanical properties of zirconium alloys are similar whether unirradiated or irradiated. Alloy B has shown the highest yield strength and tensile strength properties compared to other alloys in irradiated condition. Even though each of the zirconium alloys has a different alloying content, this content does not seem to affect the mechanical properties under an unirradiated condition and low fluence. And all the alloys have shown the tendency to increase in yield strength and ultimate tensile strength. Transverse specimens of each of the zirconium alloys have a slightly lower irradiation growth tendency than longitudinal specimens. However, for clear analysis of texture effects, further testing under higher irradiation conditions is needed.