• Title/Summary/Keyword: advanced thermal analysis

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Fabrication and Characterization of InGaN/GaN LED structures grown on selectively wet-etched porous GaN template layer

  • Beck, Seol;Cho, Yong-Hoon
    • Proceedings of the Korean Vacuum Society Conference
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    • 2010.02a
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    • pp.124-124
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    • 2010
  • Much interest has been focused on InGaN-based materials and their quantum structures due to their optoelectronics applications such as light emitting diode (LED) and photovoltaic devices, because of its high thermal conductivity, high optical efficiency, and direct wide band gap, in spite of their high density of threading dislocations. Build-in internal field-induced quantum-confined Stark effect in InGaN/GaN quantum well LED structures results in a spatial separation of electrons and holes, which leads to a reduction of radiative recombination rate. Therefore, many growth techniques have been developed by utilizing lateral over-growth mode or by inserting additional layers such as patterned layer and superlattices for reducing threading dislocations and internal fields. In this work, we investigated various characteristics of InGaN multiple quantum wells (MQWs) LED structures grown on selectively wet-etched porous (SWEP) GaN template layer and compared with those grown on non-porous GaN template layer over c-plane sapphire substrates. From the surface morphology measured by atomic force microscope, high resolution X-ray diffraction analysis, low temperature photoluminescence (PL) and PL excitation measurements, good structural and optical properties were observed on both LED structures. However, InGaN MQWs LED structures grown on SWEP GaN template layer show relatively low In composition, thin well width, and blue shift of PL spectra on MQW emission. These results were explained by rough surface of template layer, reduction of residual compressive stress, and less piezoelectric field on MQWs by utilizing SWEP GaN template layer. Better electrical properties were also observed for InGaN MQWs on SWEP GaN template layer, specially at reverse operating condition for I-V measurements.

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Modification of RFSP to Accommodate a True Two-Group Treatment

  • Bae, Chang-Joon;Kim, Bong-Ghi;Suk, Soo-Dong;D. Jenkins;B. Rouben
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.05a
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    • pp.185-190
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    • 1996
  • RFSP is a computer program to do fuel management calculations for CANDU reactors. Its main function is to calculate neutron flux and power distributions using two-energy-group, three dimensional neutron diffusion theory. However, up to now the treatment has not been true two-group but actually "one-and-half groups". In other words, the previous (1.5-group) version of RFSP lumps the fast fission term into the thermal fission term. This is based on the POWDERPUFS-V Westcott convention. Also, there is no up-scattering term or bundle power over cell flux (H1 factor) for the fast group. While POWDERPUFS-V provides only 1.5 group properties, true two-group cross sections for the design and analysis of CAUDU reactors can be obtained from WIMS-AECL. To treat the full two-group properties, the previous RFSP version was modified by adding the fast fission, up-scatter terms, and H1 factor. This two-group version of RFSP is a convenient tool to accept lattice properties from any advanced lattice code (e.g. WIMS-AECL DRAGON, HELIOS...) and to apply to advanced fuel cycles. In this study, the modification to implement the true two-group treatment was performed only in the subroutines of the *SIMULATE module of RFSP. This module is the appropriate one to modify first, since it is used for the tracking of reactor operating histories. The modified two-group RFSP was evaluated with true two-group cross sections from WIMS-AECL. Some tests were performed to verify the modified two-group RFSP and to evaluate the effects of fast fission and up-scatter for three core conditions and four cases corresponding to each condition. The comparisons show that the two-group results are quite reasonable and serve as a verification of the modifications made to RFSP. To assess the long-term impact of the full 2-group treatment, it is necessary to simulate a long period (several months) of reactor history. It will also be necessary to implement the full two-group treatment of reactivity devices and assess the reactivity-device worths.ce worths.

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Radiation attenuation and elemental composition of locally available ceramic tiles as potential radiation shielding materials for diagnostic X-ray rooms

  • Mohd Aizuddin Zakaria;Mohammad Khairul Azhar Abdul Razab;Mohd Zulfadli Adenan;Muhammad Zabidi Ahmad;Suffian Mohamad Tajudin;Damilola Oluwafemi Samson;Mohd Zahri Abdul Aziz
    • Nuclear Engineering and Technology
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    • v.56 no.1
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    • pp.301-308
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    • 2024
  • Ceramic materials are being explored as alternatives to toxic lead sheets for radiation shielding due to their favorable properties like durability, thermal stability, and aesthetic appeal. However, crafting effective ceramics for radiation shielding entails complex processes, raising production costs. To investigate local viability, this study evaluated Malaysian ceramic tiles for shielding in diagnostic X-ray rooms. Different ceramics in terms of density and thickness were selected from local manufacturers. Energy Dispersive X-ray Fluorescence (EDXRF) and X-ray Fluorescence (XRF) characterized ceramic compositions, while Monte Carlo Particle and Heavy Ion Transport code System (MC PHITS) simulations determined Linear Attenuation Coefficient (LAC), Half-value Layer (HVL), Mass Attenuation Coefficient (MAC), and Mean Free Path (MFP) within the 40-150 kV energy range. Comparative analysis between MC PHITS simulations and real setups was conducted. The C3-S9 ceramic sample, known for homogeneous full-color structure, showcased superior shielding attributes, attributed to its high density and iron content. Notably, energy levels considerably impacted radiation penetration. Overall, C3-S9 demonstrated strong shielding performance, underlining Malaysia's potential ceramic tile resources for X-ray room radiation shielding.

Synthesis and Properties of Polyurethane/Clay Nanocomposites Containing Siloxane Segment (실록산 세그먼트를 가진 폴리우레탄/점토 나노복합체의 제조 및 물성에 관한 연구)

  • Lee Jung Eun;Kim Hyung Joong
    • Polymer(Korea)
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    • v.29 no.2
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    • pp.177-182
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    • 2005
  • Montmorillonite (MMT) modified with siloxane diamine was reacted with a reactant obtained from 4,4'-diphenyl methane diisocyanate (MDI) and polyester type polyol, $Nippollan4010(\bar{M}_n2000)$. Finally, polyurethane (PU)/MMT composites were prepared by using 1,4-butane diol as a chain extender in $25\;wt\%$ solution of N,N-dimethyl acetamide (DMAc). It was expected that these nanocomposites had superior exfoliation property to that of MMT dispersed polyurethanes produced by simple mixing due to insertion of siloxane main chain to the silicate interlayer of MMT. Extent of reaction and formation of final products were analysed by using FT-IR spectroscopy. Dispersion into the PU and intercalation of MMT were identified by applying X-ray diffraction (XRD) and transmission electron microscopy (TEM). Tensile data were acquired by universal test machine (UTM). Thermal stability and variation of surface energy were characterized by thermal gravimetric analysis (TGA) method and measurement of contact angle on the synthesized composites, respectively. As the results the organo-MMT modified with siloxane diamine in the PU composites has an intercalated structure relatively well-expanded rather than a completely exfoliated structure. The tensile strengths and the moduli for the PU/organo-MMT composites were drastically enhanced in comparison to those of $PU/Na^+-MMT$ composites.

Out-of-Pile Test for Yielding Behavior of PWR Fuel Cladding Material (노외 실험을 통한 가압경수형 핵연료 피복재의 항복거동연구)

  • Yi, Jae-Kyung;Lee, Byong-Whi
    • Nuclear Engineering and Technology
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    • v.19 no.1
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    • pp.22-33
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    • 1987
  • The confirmed integrity of nuclear fuel cladding materials is an important object during steady state and transient operations at nuclear power plant. In this context, the clad material yielding behavior is especially important because of pellet-clad gap expansion. During the steep power excursion, the in-pile irradiation behavior differences between uranium-dioxide fuel pellet and zircaloy clad induce the contact pressure between them. If this pressure reaches the zircaloy clad yield pressure, the zircaloy clad will be plastically deformed. After the reactor power resumed to normal state, this plastic permanent expansion of clad tube give rise to the pellet-clad gap expansion. In this paper, the simple mandrel expansion test method which utilizes thermal expansion difference between copper mandrel and zircaloy tube was adopted to simulate this phenomenon. That is, copper mandrel which has approximately three times of thermal expansion coefficient of zircaloy-4 (PWR fuel cladding material) were used in this experiment at the temperature range from 400C to 700C. The measured plastic expansion of zircaloy outer radius and derived mathematical relations give the yield pressure, yield stress of zircaloy-4 clad at the various clad wall temperatures, the activation energy of zircaloy tube yielding, and pellet-clad gap expansion. The obtained results are in good agreement with previous experimental results. The mathematical analysis and simple test method prove to be a reliable and simple technique to assess the yielding behavior and gap expansion measurement between zircaloy-4 tube and uranium-dioxide fuel pellet under biaxial stress conditions.

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Analysis on Pool Temperature Variation along Pool Water Management System Operation in Research Reactor (연구용원자로에서 수조수관리계통 운전에 따른 수조수 온도 해석)

  • Choi, Jungwoon;Lee, Sunil;Park, Ki-Jung;Seo, KyoungWoo
    • Transactions of the KSME C: Technology and Education
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    • v.5 no.2
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    • pp.135-143
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    • 2017
  • The domestic unique research reactor, HANARO (Hi-flux Advanced Neutron Application ReactOr), has been constructed with the open-pool, the core is submerged in, for the multi-purpose neutron application. The reactor has a primary cooling system to remove the fission heat from the core and its connected fluidic systems. Since the works are required at the reactor pool top as a characteristic of the research reactor, the radiation shall be minimized with the operation of the hot water layer system to avoid unnecessary radiation exposure on the workers during work at the pool top. Moreover, the pool water management system is connected to the reactor pool to maintain the pool temperature below $50^{\circ}C$ to minimize the uprising radioactive gas or impurity from the colder pool bottom. For the efficient flow rate of the PWMS, the thermal capacity of heat exchanger is selected with 260 kW in the normal operation condition. In this paper, the modeling is formulated to figure out whether or not each pool temperature maintains below the temperature limit and the calculation results show that the designed PWMS heat exchanger has enough capacity with the design margin regardless of the reactor operation mode.

Polyether Ether Ketone Membrane with Excellent Pure Permeability Using Thermally Induced Phase Separation Method and Morphology Analysis with Characterization (열유도 상분리법을 이용한 순수 투과 성능이 우수한 폴리에테르 에테르 케톤 분리막 제조와 모폴로지 분석 및 특성평가)

  • Kwang Seop Im;Seong Jun Jang;Chae Hong Lim;Sang Yong Nam
    • Applied Chemistry for Engineering
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    • v.35 no.3
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    • pp.214-221
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    • 2024
  • Polyether ketone (PEEK) has been widely used in membranes because of its excellent thermal stability, chemical resistance, and significant mechanical strength. However, the melting temperature is very high, making it difficult to find suitable solvents. Therefore, in this study, PEEK and benzophenone (DPK) were used as diluents to prepare a membrane with excellent mechanical strength and chemical stability using the thermally induced phase separation (TIPS) method to compensate for the shortcomings of PEEK membrane preparation and achieving the highest performances. The optimal membrane manufacturing conditions were confirmed through the crystallization temperature and cloud point according to the polymer content through the phase diagram. Subsequently, the morphological changes of the membrane, influenced by the polymer and diluent content, were confirmed through scanning electron microscopy (SEM). Additionally, the membrane thickness tended to increase with higher polymer content. Tensile strength and DI-water permeability tests were conducted to confirm the mechanical strength and permeability of the membrane. Through the previous characteristic evaluation, it was confirmed that the membrane using PEEK had excellent mechanical strength and permeability.

A Study of Thermo-Mechanical Analysis for the Design of High Pressure Piping System for Natural Gas Fuel Vessel (천연가스 연료선박의 고압 이중 배관 설계를 위한 열-구조 해석에 관한 연구)

  • Park, Seong-Bo;Sim, Myung-Ji;Kim, Myung-Soo;Kim, Jeong-Hyeon;Lee, Jae-Myung
    • Journal of Advanced Marine Engineering and Technology
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    • v.39 no.4
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    • pp.425-431
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    • 2015
  • LNG (liquefied natural gas) is considered the best alternative eco-fuel, and many studies on the LNG fuel system have been performed to use LNG as the fuel for ships. For the LNG fuel supply system, natural gas transfers from the vaporizer to the engine in the gaseous state with a temperature of $50^{\circ}C$ and a pressure of 35MPa. Therefore, a structural safety evaluation of the double-walled pipelines considering thermal load is essential. In this article, an uniaxial tensile test for super duplex stainless steel, material for double-walled pipe, according to the annealing time was carried out to analyze the thermal effect. In addition, thermo-structural analysis of the high temperature-high pressure double-walled pipe with fixed supports that are now used widely was carried out to evaluate the structural safety. To minimize stress concentration of the connection point between the support and inner pipe, the shapes of the new type support that can slip through inner pipe were proposed, and the supports which has best structural performance was selected using the results from the thermo-structural analyses of new supports and an analysis of the whole double-walled pipeline was performed to ensure structural safety. These results can be used as a database for the design of double-walled pipelines and sliding support.

Numerical Analysis of Integrated Fuel Processing System Considering Thermo-Chemical Energy Balance (열/화학적 에너지 평형을 고려한 통합 연료 개질 시스템의 수치적 연구)

  • Noh, Junghun;Jung, Hye-Mi;Jung, Un-Ho;Yoon, Wang-Lai;Um, Sukkee
    • 한국신재생에너지학회:학술대회논문집
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    • 2010.11a
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    • pp.111.1-111.1
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    • 2010
  • This paper focuses on a systematic configuration of steam reforming fuel processor, particularly designed for small and medium sized hydrogen production application. In a typical integration of the fuel processor, there exist significant temperature gradients over the entire system which has negative effect on both catalyst life-time and system performance. Also, the volumetric inefficiency should be avoided to obtain the possible compactness for the commercial purpose. In the present work, the computational analysis will be performed to gain the fundamental insight on the transport phenomena and chemical reactions in the reformer consisting of preheating, steam reforming (SR), and water gas shift (WGS) reaction beds in the flow direction. Also, the fuel processing system includes a top-fired burner providing necessary thermal energy for endothermic catalytic reactor. A fully two-dimensional numerical modeling for a integrated fuel processing system is introduced for in-depth analysis of the heat and mass transport phenomena based on surface kinetics and catalytic process. In the model, water gas shift reaction and decomposition reaction were assumed to be at equilibrium. A kinetic model was developed and then computational results were compared with the experimental data available in the literature. Finally, the case study was done by considering the key parameters, i.e. steam to carbon (S/C) ratio and temperature. The computer-aided models developed in this study can be greatly utilized for the design of advanced fast-paced compact fuel processors research.

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Shape Optimization of S-tube for Heat Exchanger Used in High Temperature Environment Using FE Analysis and DOE (유한요소법과 실험계획법을 이용한 고온 열교환기용 S-관의 형상 최적화)

  • Jeong, Ho-Seung;Cho, Jong-Rae
    • Journal of Advanced Marine Engineering and Technology
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    • v.36 no.4
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    • pp.497-503
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    • 2012
  • The aim of this study was to optimize S-tube shape of heat exchanger in term of reducing the size of tube bundle and improving the mechanical properties such as the thermal stress and resonance. The geometric parameters such as offset length, the straight distance between one end and other end of tube, the tube length in straight portion and fillet radius was assessed as a valid parameters. The structural analysis was performed to estimate the structural characteristics. Main effect analysis was performed to investigate the main effect for the various geometric parameters. The response surface methodology was employed to establish mathematical approximation models as a function of the geometric parameters of the S-tube. Also, The optimization was performed to optimize geometric parameters of S-tube using the regression equations and optimization tool. The optimized tube shape has been proposed. Those could be used in the heat exchanger design used in high temperature.