• Title/Summary/Keyword: nuclear apparatus

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Injection Molded Microcellular Plastic Gear (I) - Process Design for the Microcellular Plastic Gear - (초미세발포 플라스틱 기어에 관한 연구 (I) - 초미세발포 플라스틱 기어의 공정설계 -)

  • Ha Young Wook;Chong Tae Hyong
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.29 no.5 s.236
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    • pp.647-654
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    • 2005
  • This research Proposes a Process design of injection molded microcellular plastic gears for enhancing the fatigue strength/durability and accuracy of the gears applying thermodynamic instability to microcellular foaming process. To develop the injection molded plastic gears by way of microceliular process, it is absolutely necessary the following two process design. The first is microcellular forming process for enhancing the strength/durability of plastic gears. To be microcellular process succeeded, based on the microcellular principle, mechanical apparatus is designed where nucleation and cell growth are to be generated renewably. The second is the counter pressure process which is mainly fur improving the tooth surface roughness and the accuracy of microcellular gears. For the former process, screw, nozzle and gas equipment are newly designed, and for the latter, counter pressure by nitrogen gas is intentionally brought about into mold cavity when injecting plastic gears. Based on the proposed process design, using gear mold, experiments of injection molding show that, in internal space of plastic gears, microcellular nuclear cells less than 5 lim in diameter have been generated homogeneously via electron microscope photos.

Experimental Evaluation on Structural Performance of Large Diameter Reinforcing Steel Bars with Spliced Sleeves (대구경 기계적 철근 이음장치의 구조성능에 관한 실험적 평가)

  • Kwon, Ki Joo;Park, Dong Su;Joung, Won Seoup
    • Journal of the Korea institute for structural maintenance and inspection
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    • v.15 no.1
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    • pp.180-188
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    • 2011
  • Recently a number of researches about mechanical splice have been studied to apply on a large diameter reinforcing steel bars of spliced sleeves. In this study the structural performance of large diameter reinforcing bars with spliced sleeves was evaluated. For the application of nuclear power plant structures, two different types of existing splices with #11, 14, 18 rebars were fabricated and static and dynamic test were performed on the basis of ASME SEC III DIV.2CC-4330.

The Development of Iodine-123 with MC-50 Cyclotron (MC-50 싸이클로트론을 이용한 $^{123}I$ 제법 연구)

  • Suh, Yong-Sup;Yang, Seung-Tae;Chun, Kown-Soo;Lee, Jong-Doo;Han, Hyon-Soo
    • The Korean Journal of Nuclear Medicine
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    • v.25 no.2
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    • pp.286-293
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    • 1991
  • $^{123}I$, which is applied for the thyroid and other in vivo kinetic study, has a special role in life sciences. The 159 KeV $\gamma-ray$ from $^{123}I$ is almost ideally appropriate for the current imaging instrumentation. Its decay mode (electron capture) and short half-life (13.3 hr) reduced the burden of radiation dose to the patients, and its chemical property makes it easy to synthesize the labelling compounds. In this experiment, the production of $^{123}I$ via the nuclear reaction $^{124}Te(p,2n)^{123}I$ with 28 MeV protons was sutdied. $TeO_2$ is used as a target material, because it has good physical properties. The target was prepared with $TeO_2$ powder and was molten into a ellipsoidal cavity (a=14 mm, b=10 mm, $270.8mg/cm^2$ thick) of pure platinum. The irradiation was carried out in the external proton beam with incident energies range from 28 MeV to 22 MeV, and current was $30{\mu}A$. The loss of $TeO_2$ target was significantly reduced by using $4\pi-cooling$ system in irradiation. The dry distillation method was adopted for the separation of $^{123}I$ from irradiated target, and when it was kept 5 minutes at $780^{\circ}C$, its result was quantitative. The loss of the target material $(TeO_2)$ was below 0.2% for each production run and $^{123}I$ from the dry distillation apparatus was captured with 0.01 N NaOH in $Na^{123}I$ form, then the pH of the solution was adjusted to $7.5\sim9.0$ with HC1/NaOH. The $Na^{123}I$ solution was passed through $0.2{\mu}m$ membrane filter, and sterilized under high pressure and temperature for 30 minutes. The production of $^{123}I$ is acceptable for clinical application based on the quality of USP XXI.

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Development of the Pushing Type Cutting Device to Dismantle Concrete Structure for Decommissioning of Nuclear Power Plant (원전해체 시 콘크리트 구조물 절단을 위한 밀기형 절단장치 개발)

  • Lee, Bong-Jae;Kwon, Yong-Kyu;Hong, Chang-Dong;Lee, Dong-Won;Min, Kyong-Nam
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.18 no.1
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    • pp.103-111
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    • 2020
  • Pulling-type cutting devices, which use a diamond wire saw, have been used generally for cutting concrete structures. In this study, a pushing-type cutting device with a collection cover was developed by overcoming the disadvantages of pulling-type devices. In this device, dry or liquid methods can be selected to cool frictional heat. Operation and leakage tests of the dust generated during the dismantling of a concrete structure were carried out, confirming the suitable operation of the fabricated cutting device; the leakage rate was approximately 1.7%. For a conservative evaluation, the internal dose of workers was estimated in dismantling the core center part of biological shield concrete with a specific activity of 99.5 Bq·g-1. The committed effective dose per worker was 0.25 mSv. The developed cutting device contributed to reducing radioactive concrete waste and minimizing worker exposure due to its easy installation. Therefore, it can be utilized as a cutting apparatus for dismantling not only reinforced concrete structures but also radioactive biological shield concrete in nuclear power plant decommissioning efforts.

An Ultrastructural Study on the Effect of Exogenous $Ca^{2+}$ Stimulation to Ischemic Myocardium during Post-ischemic Reperfusion (재관류시 외인성 칼슘 자극이 허혈 심근에 미치는 영향에 대한 전자현미경적 연구)

  • Kim, Ho-Dirk;Chun, Sang-Bae;Rah, Bong-Jin
    • Applied Microscopy
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    • v.21 no.1
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    • pp.1-20
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    • 1991
  • The effects of exogenous $Ca^{2+}$ stimulation on the post-ischemic myocardial cells were studied using isolated Langendorff-perfused guinea pig hearts. At the starting point of reperfusion, Tyrode solutions, each containing 2.0mM, 4.0mM and 8.0mM $CaCl_2$ respectively, were administered for 2 minutes apart by descending, ascending, or by combined sequences followed by standard Tyrode solution containing 1.0mM $CaCl_2$. The minutes of global ischemia produced reversible but moderate to severe degree of myocardial ultrastructrual changes including focal destruction of sarcolemma, loss of nuclear matrix, clumping and margination of chromatins, mitochondrial swelling, destruction of mitochondrial cristae, shortening of sarcomeres, focal loss of myofibrils, and separation of cell junctions. In spite of reperfusion, the ultrastructure was more severely damaged and irreversible changes such as intracellular fluid accumulation, contracted sarcomeres, mitochondrial destruction, disruption of sarcolemma, loss of nuclear matrix, and separation of cell junction were observed in a large number of cells. In contrast, Tyrode-perfused $Ca^{2+}$-stimulated myocardial cells showed relatively well preserved ultrastucture, except slight changes including focal mitochondrial swelling, widening of T-tubule, and widening of cell junctions, especially at fasciae adherentes. The post-ischemic $Ca^{2+}$-stimulated reperfused myocardial cells produced focal changes such as mitochondrial destruction, disintegration of sarcolemma, widening of T-tubule, and intracellular fluid accumulation with slight variation in degree of changes by the method of $Ca^{2+}$ administration sequence. However, in a large number of the myocardial cells, chromatins were redistributed relatively evenly in the nuclear matrix, mitochondrial cristae were tightly packed, and a considerable number of intramitochondrial granules and glycogen granules reap-pealed. These results indicate that exogenous $Ca^{2+}$ stimulation in the initial period of reperfusion may be beneficial to salvage or to reduce the post-ischemic myocardium from further deleterious changes, and that the beneficial effects may be derived from the reserves of the function of the intracellular $Ca^{2+}$ regulating organelles and/or from the responsiveness of contractile apparatus to $Ca^{2+}$ stimulation.

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Study of morphology on the Oxidation and the Annealing of High Burn-hp $UO_2$ Spent Fuel (고연소도 사용후 핵연료의 가열산화와 고온가열을 통한 미세조직 변화고찰)

  • Kim Dae Ho;Bang Jae Geun;Yang Yong Sik;Song Keun Woo;Lee Hyung Kwon;Kwon Hyung Moon
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.3 no.4
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    • pp.301-307
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    • 2005
  • The morphology of the high burnup $UO_2$ spent fuel, which was oxidized and annealed in a PIA (Post Irradiation Annealing) apparatus, has been observed. The high burnup fuel irradiated in Ulchin Unit 2, average rod burnup 57,000 MWd/tU, was transported to the KAERI's PIEF. The test specimen was used with about 200 mg of the spent $UO_2$ fuel fragment of the local burnup 65,000 MWd/tU. This specimen was annealed at $1400^{\circ}C$ for 4hrs after the oxidation for 3hrs to grain boundary using the PIA apparatus in a hot-cell. In order to oxidize the grain boundary, the oxidation temperature increased up to $500^{\circ}C$ and held for 3hrs in the mixed gas (60 ml He and 100 ml STD-air) atmosphere. The amount of 85Kr during the whole test process was measured to know the fission gas release behavior using the online system of a beta counter and a gamma counter. The detailed micro-structure was observed by a SEM to confirm the change of the fuel morphology after this test. As the annealing temperature increased, the fission products were observed to move to the grain surface and grain boundary of the $UO_2$ matrix. This specimen was re-structured through the reduction process, and the grain sizes were distributed from 5 to $10\;{\mu}m$.

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Radioactivation Analysis of Concrete Shielding Wall of Cyclotron Room Using Monte Carlo Simulation (PET 사이클로트론 가동에 따른 콘크리트 차폐벽의 방사화)

  • Jang, Donggun;Lee, Dongyeon;Kim, Junghoon
    • Journal of the Korean Society of Radiology
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    • v.11 no.5
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    • pp.335-341
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    • 2017
  • Cyclotron is a device that accelerates positrons or neutrons, and is used as a facility for making radioactive drugs having short half-lives. Such radioactive drugs are used for positron emission tomography (PET), which is a medical apparatus. In order to make radioactive drugs from a cyclotron, a nuclear reaction must occur between accelerated positrons and a target. After the reaction, unncessary neutrons are produced. In the present study, radioactivation generated from the collisions between the concrete shielding wall and the positrons and neutrons produced from the cyclotron is investigated. We tracked radioactivated radioactive isotopes by conducting experiments using FLUKA, a type of Monte Carlo simulation. The properties of the concrete shielding wall were comparatively analyzed using materials containing impurities at ppm level and materials that do not contain impurities. The generated radioactivated nuclear species were comparatively analyzed based on the exposure dose affecting human body as a criterion, through RESRAD-Build. The results of experiments showed that the material containing impurities produced a total of 14 radioactive isotopes, and $^{60}Co$(72.50%), $^{134}Cs$(16.75%), $^{54}Mn$(5.60%), $^{152}Eu$(4.08%), $^{154}Eu$(1.07%) accounted for 99.9% of the total dose according to the analysis having the exposure dose affecting human body as criterion. The $^{60}Co$ nuclear species showed the greatest risk of radiation exposure. The material that did not contain impurities produced a total of five nuclear species. Among the five nuclear species, 54Mn accounted for 99.9% of the exposure dose. There is a possibility that Cobalt can be generated by inducive nuclear reaction of positrons through the radioactivation process of $^{56}Fe$ instead of impurities. However, there was no radioactivation because only few positrons reached the concrete wall. The results of comparative analysis on exposure dose with respect to the presence of impurities indicated that the presence of impurities caused approximately 98% higher exposure dose. From this result, the main cause of radioactivation was identified as the small ppm-level amount of impurities.

Hormonal Activity of Ovarian Fibroma and Thecoma (난소 섬유종과 포막종의 호르몬 분비능에 관한 연구)

  • Lee, Soong-Deok;Suh, Jin-Suk;Han, Young-Mee;Kim, Jung-Ran;Seo, Jeong-Wook;Ham, Eui-Keun;Lee, Hyo-Pyo
    • Applied Microscopy
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    • v.19 no.1
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    • pp.27-33
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    • 1989
  • Six cases of ovarian fibrous stromal neoplasm were studied clinically, light microscopically and ultrastructurally for the clinico-pathological evidences of hormone production. Of the six cases, two cases were fibroma, three cases were fibrothecoma, and one case was thecoma. Two cases of fibroma and one fibrothecoma were associated with clinical history of menstrual abnormality, however fat staining of the tumor was negative or weakly positive. Two cases of fibrothecoma and one thecoma were negative for the clinical history of hormone imbalance. Fat stain of those cases revealed positive in varying intensity. Ultrastructural examination of fibroma-thecoma group revealed dark and pale cells by their nuclear characteristics. The dark cells had indented nucleus and abundant cytoplasmic organelles of rough ER, Golgi apparatus and mitochondria. Intracytoplasmic cisternal spaces were seen in the dark cell cytoplasm and some lipid droplets were seen around the cisternae. Pale cells had pale swollen nucleus and fine chromatins. Their cytoplasm showed scanty amount of organelles. Fibroma-thecoma spectrum showed varying degree of population of dark cells, light cells and intervening collagenous stroma. Lipid droplet was structurally associated with intracytoplasmic cisterna and they were frequently seen in thecoma and two of the fibrothecoma. But clinical history of hormone imbalance was poorly related to the light microscopic morphology and ultrastructural organization.

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Consolidation and Strength Properties of Clay Subjected to High Temperature Histories (고온이력을 받는 점토의 압밀 및 전단특성)

  • Lee Kang-Il
    • Journal of the Korean Geotechnical Society
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    • v.21 no.4
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    • pp.41-49
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    • 2005
  • Recently, ground has been often exposed to high temperature environments such as chemical ground improvement, thermal energy storage system, and underground nuclear waste disposal system. Since the behavior of clay is sensitive to temperature change, the studies on the engineering properties of clay subjected to high temperature history may be important. This paper presents the mechanical behavior of clay with high temperature condition. $\bar{CU}$ tests using a high temperature and pressure triaxial compression test apparatus were carried out in order to investigate characteristics of deformation, shear strength, compression and consolidation of clay. During tests, the temperature was varied from $20^{\circ}C,\;50^{\circ}C,\;75^{\circ}C,\;80^{\circ}C\;to\;100^{\circ}C$.

Detection of Colloidal Nanoparticles in KURT Groundwater by a Mobile Laser-Induced Breakdown Detection System (이동식 레이저 유도 파열 검출 장치를 이용한 KURT 지하수 내 콜로이드 나노 입자 검출)

  • Jung, Euo-Chang;Cho, Hye-Ryun;Park, Mi-Ri;Baik, Min-Hoon
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.9 no.1
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    • pp.41-48
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    • 2011
  • A mobile laser-induced breakdown detection (LIBD) system was developed for the field measurement of the size and concentration of aquatic colloidal nanoparticles sampled from Korea Atomic Energy Research Institute Underground Research Tunnel (KURT). The established LIBD apparatus is based on the optical detection of a laser-induced plasma by means of a two-dimensional optical imaging method for determining the size of nanoparticle. Calibration curve for determining the size of nanoparticle was obtained from the polystyrene reference particles of a well-defined size. The first direct application was made at KURT for investigating the particle sizes in groundwater. By comparing the size of particles in groundwater with the sizes of reference particles, the mean particle size of approximately $108{\pm}26$ nm with the concentration lower than 50 ppb was determined.