• Title/Summary/Keyword: Nuclear generation

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A Study of the Improvement of Clinical and Practical Trainings in the Education of Radiologic Technologists (방사선사(放射線士) 교육(敎育)의 임상실습(臨床實習) 개선(改善)에 관(關)한 연구(硏究))

  • Lee, Man-Koo;Kang, Se-Sik;Yoon, Han-Sik;Huh, Joon
    • Journal of radiological science and technology
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    • v.6 no.1
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    • pp.117-129
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    • 1983
  • This study, in order to improve clinical and practical trainings in the education of radiologic technologists, applies to 76 medical institutions of 91 ones which are used as the hospitals of clinical and practical training in 9 existing junior colleges except 3 new ones of 12 ones throughout all over the country from November 1, in 1982 to April 30, in 1983. And the purpose of this study is to research the percent conditions of basic practical trainings and clinical ones enforced in each college, and the percent conditions, equipments, contents, and opinions in clinical and practical trainings enforced in each hospital. The results are summarized as follows; 1. In the case of junior colleges in the whole country the curriculum of basic practical trainings averages 336.66 hours and the limits are between 120 and 510 hours. The actual hours in practice average 140 hours and the limits are between 60 and 240 hours, which correspond to 41.58% of the curriculum of basic practical trainings. 2. There were three junior colleges among nine that had a reserved hospital for clinical and practical trainings(only 33.33%). 3. The period of the practice was almost vacation in 4 junior colleges. The practice was conducted only for students to want the practice(44.45%), junior colleges that all students in them conducted the practice was 2 junior colleges and presented 22.22%. 4. In the field of students engaging in the practice, each field of radiation therapy and nuclear medicine presented 16.5%, 20.3% and almost students didin't have experience for the practice. 5. In medical institutions the educational institutions for intern showed 67.11%. Hospital with radiologist showed 26.32%. Radiotechnologist who had experience below 5 years presented 60.17%. 6. In the equipment for radiation diagnosis, each hospital had no difference. The number of hospitals passessing diagnostic equipments above 125 KVP was 56.26%. But radiation therapy equipment and nuclear medicine equipment had extremely low rate. 7. In the diagnosis of patient in the practice hospital, conventional radiography-to Skull, Chest, Abdomen, Skeleton, Urogenital system-reached the criterion. But special radiography was comparatively low. There appeared low rate, 32.89% in the field of nuclear medicine, 15.79% in the field of radiation therapy. 8. Students who carried out the practice were 1-89 students, days in practice were 1-30 days. There were differences in that point among among hospitals. Junior colleges conducting the practice were 2 colleges per hospital. Scope of the object were 1-8 junior colleges. 9. The practice conducted for the request of the colleges presented 72.37%, in addition, The prctices were conducted for growth of the younger generation and the same coperation with the colleges establishment of sisterhood with the colleges, relationship with students. 10. The practice conducted without the establishment of plan presented 59.21% The need for guiding book to the practice and evaluating was recognized over 90%. 11. In the relation between the practice with achievement of credit. There were big differences in opinion between hospitals-Group and the colleges-Group; hospital-Group had opinion that must follow achievement of credit with the practice. The colleges-Group had opinion that must conduct the practice after achieving credit. 12. After conducting the practice, in the practice leaders satisfaction degree dissatisfactory opinion presented the most rate 80.26%. Very much satisfactory opinion, as one hospital, presentd only 1.32%. 13. Both hospitals-Group and the colleges-Group had an opinion that the practice leader must have actual experiences, lectures and achievement, an opinion that actual experiences is over 5 years. 14. In the guide of human relation, cooperation, responsibility, courtesy to patients. Both hospitals-Group and the colleges-Group had an opinion that the guide must be involved in the period of the practice and must be instructed.

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Removal of Cs by Adsorption with IE911 (Crystalline Silicotitanate) from High-Radioactive Seawater Waste (IE911 (crystalline silicotitanate) 의한 고방사성해수폐액으로부터 Cs의 흡착 제거)

  • Lee, Eil-Hee;Lee, Keun-Young;Kim, Kwang-Wook;Kim, Ik-Soo;Chung, Dong-Yong;Moon, Jei-Kwon
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.13 no.3
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    • pp.171-180
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    • 2015
  • This study was performed on the removal of Cs, one of the main high- radioactive nuclides contained in the high-radioactive seawater waste (HSW), by adsorption with IE911 (crystalline silicotitanate type). For the effective removal of Cs and the minimization of secondary solid waste generation, adsorption of Cs by IE911 (hereafter denoted as IE911-Cs) was effective to carry out in the m/V (ratio of absorbent weight to solution volume) ratio of 2.5 g/L, and the adsorption time of 1 hour. In these conditions, Cs and Sr were adsorbed about 99% and less than 5%, respectively. IE911-Cs could be also expressed as a Langmuir isotherm and a pseudo-second order rate equation. The adsorption rate constants (k2) were decreased with increasing initial Cs concentrations and particle sizes, and increased with increasing ratios of m/V, solution temperatures and agitation speeds. The activation energy of IE911-Cs was about 79.9 kJ/mol. It was suggested that IE911-Cs was dominated by a chemical adsorption having a strong bonding form. From the negative values of Gibbs free energy and enthalpy, it was indicated that the reaction of IE911-Cs was a forward, exothermic and relatively active at lower temperatures. Additionally, the negative entropy values were seen that the adsorbed Cs was evenly distributed on the IE911.

CFD Analysis to Suppress Condensate Water Generated in Gas Sampling System of HANARO (하나로 기체시료채취계통에서 생성된 응축수 억제를 위한 CFD 해석)

  • Cho, SungHwan;Lee, JongHyeon;Kim, DaeYoung
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.18 no.2_spc
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    • pp.327-336
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    • 2020
  • The high-flux advanced neutron application reactor (HANARO) is a research reactor with thermal power of 30 MW applied in various research and development using neutrons generated from uranium fission chain reaction. A degasifier tank is installed in the ancillary facility of HANARO. This facility generates gas pollutants produced owing to internal environmental factors. The degasifier tank is designed to maintain the gas contaminants below acceptable levels and is monitored using an analyzer in the gas sampling panel. If condensate water is generated and flows into the analyzer of the gas sampling panel, corrosion occurs inside the analyzer's measurement chamber, which causes failure. Condensate water is generated because of the temperature difference between the degasifier tank and analyzer when the gas flows into the analyzer. A heating system is installed between the degasifier tank and gas sampling panel to suppress condensate water generation and effectively remove the condensate water inside the system. In this study, we investigated the efficiency of the heating system. In addition, the variations in the pipe temperature and the amount of average condensate water were modeled using a wall condensation model based on the changes in the fluid inlet temperature, outside air temperature, and heating cable-setting temperature.

Research of Wall Storage System design process for residential space (주문형 주거공간에서 Wall Storage System을 활용한 가변화 방안 연구)

  • 임은상
    • Archives of design research
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    • v.13 no.3
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    • pp.281-292
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    • 2000
  • Today, the rapid economic growth and emerging new trends have been changed radically throughout the society and they especially have affected the changes of life-style and the diversity of residents'demands in housing life. This changes of life have brought the shift in family form from traditional type, thus new phase of nuclear family means that it makes on the whole, variable family forms such as single family, non-blood one, a generation one and so on. It therefore is time that we should not only explore current housing plans, but envisage concept of new living space to satisfy latent need of the occupants. But the forms, in spite of the diversity of user's needs and the change of life-style, of many houses as many apartment and tenement houses supplied so far have been clearly limted, and housing policy of the mass-supply causes monotonous space composition, over-occupation and non-changeability. Now, the collective houses have some limits owing to the commoness and assemblage, but they have failed to keep up with the variable and changeable life-style of residents. These problems, to put it concretely, lead to increasing needs for the number of rooms in proportion to family members, for the change of behavior using the space. We therefore need to propose the new living space. As the current plans for designing house are based on the average life-style of people, they can not cope with variable demands of the resident. For that reason, this paper will propose the manual space system as an alternative for it and the goal is to suggest new furniture system which we need to create the flexibility of living space.

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Analytical Approach for the Noise Properties and Geometric Scheme of Industrial CR Images according to Radiation Intensity (산업용 CR영상의 방사선 강도에 따른 잡음특성과 기하학적 구도형성의 해석적 접근)

  • Hwang, Jung-Won;Hwang, Jae-Ho;Park, Sang-Ki
    • Journal of the Institute of Electronics Engineers of Korea SP
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    • v.46 no.1
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    • pp.56-62
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    • 2009
  • In this paper we investigate an analytical approach for noise properties and geometric structure in Computed Radiography(CR) images of industrial steel-tubes. Over thirty diverse radiographic images are sampled from industrial radiography measurements according to radiation intensity. Each image consists of three regions; background, thickness and inner-tube. Among these the region of inner-tube is selected for the object of analysis. Geometric structure which includes the noise generation is analyzed by the statistical and functional methodology. The analysis is carried on spacially and line by line. It verifies the geometrical transfigure from the circle configuration of steel-tube and noise variation. The estimation of fitting function and its error are the geometric factors. The statistics such as standard deviation, mean and signal-to-noise ratio are noise parameters for discrimination. These factors are considered under the intensity variation which is the penetrative strength of radiation. The analysing results show that the original geometry of circle is preserved in the form of elliptic or short/long diameter circle, and the noise deviation has increased inverse proportional to the radiation intensity.

The Effects of Injinchunggan-tang(Yinchenqinggan-tang) on $TNF-\alpha$ signal transmission system in HepG2 cell (인진청간탕(茵蔯淸肝湯)이 HepG2 cell의 $TNF-\alpha$ 신호전달계에 미치는 영향(影響))

  • Kang Woo-Sung;Kim Young-Chul;Lee Jang-Hoon;Woo Hong-Jung
    • The Journal of Internal Korean Medicine
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    • v.25 no.1
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    • pp.28-45
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    • 2004
  • Objectives : The main purpose of this study is to evaluate the effect of Injinchunggan-tang on $TNF-{\alpha}$ signal transmission system. Materials and Methods : We analyzed the following with quantitative RT-PCR method; the effect of Injinchunggan-tang on secretion of $TNF-\alpha$ mRNA/protein and stability, the effect on gene revelation that consists of signal transmission system (TRAIL, NIK, A20, TRADD, RAIDD, RIP TNFR-I, TNFR-II, TRAF1, TRAF2, FADD), the one on activation of p38, Erk1/2 MAPK and the rate of nuclear $NF-{\kappa}B/cytosolic\;NF-{\kappa}B$ in HepG2 cell. We also analyzed the inhibitory effect of Injinchunggan-tang on the apoptosis of HepG2 cell that $TNF-{\alpha}$ induces and the $NF-{\kappa}B$ restraint effected by transfection of $I{\kappa}B{\Delta}N$ through tryphan blue exclusion assay. Results : Injinchunggan-tang prohibits revelation of $TNF-{\alpha}$ mRNA in HepG2 cell and the creation of protein. However, it has no effect on the stability of $TNF-{\alpha}$ mRNA. While it did not have any effect on the generation of TRAIL, NIK, A20, TRADD, RAIDD and RIP genes, Injinchunggan-tang reduces the revelation of TNFR-I, TNFR-II, TRAF1, TRAF2 and FADD genes. It has been confirmed that Injinchunggan-tang restraints the revelation of $TNF-{\alpha}$ mRNA that is promoted by ethanol, acetaldehyde, lipopolysaccharide, in proportion to the treatment density and time. It activated $NF-{\kappa}B$ of HepG2 cell and promoted activation of $NF-{\kappa}B$ that is occurred by $TNF-{\alpha}$. It has been observed that the restraint effect against the $TNF-{\alpha}$ inducing apoptosis is lost when it is intercepted the function of $NF-{\kappa}B$ in HepG2 cell. Conclusion: It has been confirmed that Injinchunggan-tang has restraining effect against the revelation of $TNF-{\alpha}$ and mRNA that is constituent element of TNF-a signal transmission system. It also has been revealed that it restraints the activation of p38, Erk1/2 by $TNF-{\alpha}$. Through this prohibiting effect, it is inferred that it restraints signal transmission among various cells that are related to inflammation reaction. Meanwhile, Injinchunggan-tang protects liver cell from apoptosis that is caused by $TNF-{\alpha}$, by maintaining the activating function for $NF-{\kappa}B$.

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Performance Analysis of CHP(Combined Heat and Power) for Various Ambient Conditions (외기조건변화에 따른 CHP 성능 해석)

  • Jeon, Yong-Han;Kim, Jong-Yoon;Kim, Nam-Jin;Lim, Kyung-Bum;Seo, Young-Ho;Kim, Ki-Hwan
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.12 no.8
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    • pp.3353-3359
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    • 2011
  • The co-generation system consisted of gas a turbine, a steam turbine, heat recovery steam generator and a heat exchangers for district heating was investigated in the present study. A back-pressure steam turbine (non-condensing type) was used. A partial load analysis according to the outdoor temperature in winter was conducted and optimal thermal load and power conditions was examined using the commercial computing software Thermoflex. As a result, under a constant thermal load, the power outputs of gas turbine and overall system increased as an outdoor temperature decreased. On the other hand, the reduction in exhaust gas temperature led to the decrease in output of steam turbine. Considering the portion of gas turbine in overall system in terms of the power output, it can be known that the tendency in power output of overall system was similar to that of the gas turbine.

Experimental Study of Characteristics of Three-Ring Impedance Meter and Dependence of Characteristics on Electric Conductivity of Fluids (3-ring 임피던스미터의 유체 전기 전도도 독립성에 대한 실험적 연구)

  • Kim, Jong-Rok;Ahn, Yeh-Chan;Kim, Moo-Hwan
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.34 no.11
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    • pp.1027-1033
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    • 2010
  • A two-phase (gas-liquid) flow is a common phenomenon in fluidic systems, e.g., fluidic systems in the electro-magnetic or nuclear power generation industry and in the steel industry. The measurement of a two-phase flow is important for guaranteeing the safety of the system and for achieving the desired performance. The measurement of the void fraction, which is one of the parameters of the two-phase flow that determines the pressure drop and heat transfer coefficient, is very important. The time resolution achieved by employing the impedance method that can be used to calculate the void fraction from the impedance of the fluid is high because the electric characteristics are taken into account. Therefore, this method can be employed to accurately measure the void fraction without distortion of flow in real time by placing electrodes on the walls of the tubes. Coney analytically studied a ring-type impedance meter, which can be employed in a circular tube. The aim of this study is to experimentally verify the robustness of a three-ring impedance meter to variations in the electric conductivity of the fluid; this robustness was suggested by Coney but was not experimentally verified.

On the Statistical Properties of the Parameters B and q in Creep Crack Growth Law, da/dt=B(C*)q, in the Case of Mod. 9Cr-1Mo Steel (Mod. 9Cr-1Mo강의 크리프 균열 성장 법칙의 파라메터 B와 q의 통계적 성질에 관한 연구)

  • Kim, Seon-Jin;Park, Jae-Young;Kim, Woo-Gon
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.35 no.3
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    • pp.251-257
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    • 2011
  • This paper deals with the statistical properties of parameters B and q in the creep crack growth rate (CCGR) law, da/dt=B$(C^*)^q$, in Mod. 9Cr-1Mo (ASME Gr.91) steel which is considered a candidate materials for fabricating next generation nuclear reactors. The CCGR data were obtained by creep crack growth (CCG) tests performed on 1/2-inch compact tension (CT) specimens under an applied load of 5000N at a temperature of $600^{\circ}C$. The CCG behavior was analyzed statistically using the empirical equation between CCGR, da/dt and the creep fracture mechanics parameter, $C^*$. The B and q values were determined for each specimen by the least-squares fitting method. The probability distribution functions for B and q were investigated using normal, log-normal, and Weibull distributions. As far as this study is considered, it can be appeared that B and q followed the log-normal and Weibull distributions. Moreover, a strong positive linear correlation was found between B and q.

Quantitative EC Signal Analysis on the Axial Notch Cracks of the SG Tubes (SG Tube 축방향 노치 균열의 정량적 EC 신호평가)

  • Min, Kyong-Mahn;Park, Jung-Am;Shin, Ki-Seok;Kim, In-Chul
    • Journal of the Korean Society for Nondestructive Testing
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    • v.29 no.4
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    • pp.374-382
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    • 2009
  • Steam generator(SG) tube, as a barrier isolating primary to the secondary coolant system of nuclear power plants(NPP), must maintain the structural integrity far the public safety and its efficient power generation capacity. And SG tubes bearing defects must be timely detected and taken repair measures if needed. For the accomplishment of these objectives, SG tubes have been periodically examined by eddy current testing(ECT) on the basis of administrative notices and intensified SG management program(SGMP). Stress corrosion cracking(SCC) on the SG tubes is not easily detected and even missed since it has lower signal amplitude and other disturbing factors against its detection. However once SCC is developed, that can cause detrimental affects to the SG tubes due to its rapid propagation rate. Accordingly SCC is categorized as prime damage mechanism challenging the soundness of the SG tubes. In this study, reproduced EDM notch specimens are examined for the detectability and quantitative characterization of the axial ODSCC by +PT MRPC probe, containing pancake, +PT and shielded pancake coils apart in a single plane around the circumference. The results of this study are assumed to be applicable fur providing key information of engineering evaluation of SCC and improvement of confidence level of ECT on SG tubes.