• Title/Summary/Keyword: advanced thermal analysis

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Thermal post-buckling analysis of uniform slender functionally graded material beams

  • Anandrao, K. Sanjay;Gupta, R.K.;Ramchandran, P.;Rao, G. Venkateswara
    • Structural Engineering and Mechanics
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    • v.36 no.5
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    • pp.545-560
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    • 2010
  • Two or more distinct materials are combined into a single functionally graded material (FGM) where the microstructural composition and properties change gradually. Thermal post-buckling behavior of uniform slender FGM beams is investigated independently using the classical Rayleigh-Ritz (RR) formulation and the versatile Finite Element Analysis (FEA) formulation developed in this paper. The von-Karman strain-displacement relations are used to account for moderately large deflections of FGM beams. Bending-extension coupling arising due to heterogeneity of material through the thickness is included. Simply supported and clamped beams with axially immovable ends are considered in the present study. Post-buckling load versus deflection curves and buckled mode shapes obtained from both the RR and FEA formulations for different volume fraction exponents show an excellent agreement with the available literature results for simply supported ends. Response of the FGM beam with clamped ends is studied for the first time and the results from both the RR and FEA formulations show a very good agreement. Though the response of the FGM beam could have been studied more accurately by FEA formulation alone, the authors aim to apply the RR formulation is to find an approximate closed form post-buckling solutions for the FGM beams. Further, the use of the RR formulation clearly demonstrates the effect of bending-extension coupling on the post-buckling response of the FGM beams.

Growth of Graphene Films from Solid-state Carbon Sources

  • Kwak, Jinsung;Kwon, Tae-Yang;Chu, Jae Hwan;Choi, Jae-Kyung;Lee, Mi-Sun;Kim, Sung Youb;Shin, Hyung-Joon;Park, Kibog;Park, Jang-Ung;Kwon, Soon-Yong
    • Proceedings of the Korean Vacuum Society Conference
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    • 2014.02a
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    • pp.181.2-181.2
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    • 2014
  • A single-layer graphene has been uniformly grown on a Cu surface at elevated temperatures by thermally processing a poly (methyl methacrylate) (PMMA) film in a rapid thermal annealing (RTA) system under vacuum. The detailed chemistry of the transition from solid-state carbon to graphene on the catalytic Cu surface was investigated by performing in-situ residual gas analysis while PMMA/Cu-foil samples being heated, in conjunction with interrupted growth studies to reconstruct ex-situ the heating process. We found that the gas species of mass/charge (m/e) ratio of 15 ($CH_3{^+}$) was mainly originated from the thermal decomposition of PMMA, indicating that the formation of graphene occurs with hydrocarbon molecules vaporized from PMMA, such as methane and/or methyl radicals, as precursors rather than by the direct graphitization of solid-state carbon. We also found that the temperature for dominantly vaporizing hydrocarbon molecules from PMMA and the length of time, the gaseous hydrocarbon atmosphere is maintained, are dependent on both the heating temperature profile and the amount of a solid carbon feedstock. From those results, we strongly suggest that the heating rate and the amount of solid carbon are the dominant factors to determine the crystalline quality of the resulting graphene film. Under optimal growth conditions, the PMMA-derived graphene was found to have a carrier (hole) mobility as high as ${\sim}2,700cm^2V^{-1}s^{-1}$ at room temperature, which is superior to common graphene converted from solid carbon.

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Development of a computer code for thermal-hydraulic design and analysis of helically coiled tube once-through steam generator

  • Zhang, Yaoli;Wang, Duo;Lin, Jianshu;Hao, Junwei
    • Nuclear Engineering and Technology
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    • v.49 no.7
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    • pp.1388-1395
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    • 2017
  • The Helically coiled tube Once-Through Steam Generator (H-OTSG) is a key piece of equipment for compact small reactors. The present study developed and verified a thermal-hydraulic design and performance analysis computer code for a countercurrent H-OTSG installed in a small pressurized water reactor. The H-OTSG is represented by one characteristic tube in the model. The secondary side of the H-OTSG is divided into single-phase liquid region, nucleate boiling region, postdryout region, and single-phase vapor region. Different heat transfer correlations and pressure drop correlations are reviewed and applied. To benchmark the developed physical models and the computer code, H-OTSGs developed in Marine Reactor X and System-integrated Modular Advanced ReacTor are simulated by the code, and the results are compared with the design data. The overall characteristics of heat transfer area, temperature distributions, and pressure drops calculated by the code showed general agreement with the published data. The thermal-hydraulic characteristics of a typical countercurrent H-OTSG are analyzed. It is demonstrated that the code can be utilized for design and performance analysis of an H-OTSG.

Heat Transfer Analysis of a Thermal Storage System using the Ice Capsule of Bar and Ring Module (봉과 링 조합형 아이스캡슐을 적용한 축열시스템의 열전달 해석)

  • Kim, Myoung-Su;Choi, Hyoung-Gwon;Byon, Sung-Kwang
    • Journal of Advanced Marine Engineering and Technology
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    • v.32 no.2
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    • pp.268-275
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    • 2008
  • The shape and array of ice capsules are very important factors in ice thermal storage system because the heat transfer rate of the system strongly depends upon them. In this paper, a new type of ice capsule composed of bar and ring module is proposed to increase the efficiency of the ice thermal storage system. To investigate the heat transfer rate of the proposed ice capsule, numerical analysis of the incompressible Navier-Stokes equations is performed to compare the proposed bar and ring system with the conventional ice capsules. It is shown that the ice capsule composed of bar and ring has a higher heat transfer rate and a low outlet temperature than the conventional ice capsules for various packing ratios and entrance velocities. Furthermore, it is found that the optimal entrance velocity exists between 0.005 m/s and 0.007 m/s from the present numerical analysis.

Analysis of Thermal Characteristics for the Fire Risk Assessment According to Partial Disconnection on the VCTF and IV Electric Wire (VCTF와 IV전선의 반단선에 의한 화재위험성 평가를 위한 열적특성 해석)

  • Kim, Doo-Hyun;Kim, Sung-Chul;Lee, Jong-Ho;Park, Jong-Young;Park, Young-Ho;Lee, Hyung-Jun
    • Journal of the Korean Society of Safety
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    • v.23 no.4
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    • pp.47-52
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    • 2008
  • Many researches on fire risk for normal electric wiring have been pursued in advanced countries such as the USA and Japan, but comparative studies of the partial disconnection and normal state of electric wires have not been conducted. Detection system for the cause of partial disconnection is not developed and prevention countermeasure for electrical fire by the cause is not effective. Therefore, in this paper, partial disconnection characteristics on electric wires were derived and analyzed by experiment and electrical-thermal finite element method(Flux 3D) on the model wires which consist of VCTF(PVC insulated PVC sheathed Cap Tyre Flexible Cord, KS C 3304) and IV(lndoorwire PVC, KS C 3302). VCTF is used in wiring portable electric appliances and the IV is used indoors. Interrelationships between partial disconnection premonitory symptom and current were derived and analyzed by the characteristics based on experiments and thermal analysis for electric wire according to current under normal state and 200% overload state of rated current.

Evaluation of Creep-Fatigue Damage of KALIMER Reactor Internals Using the Elastic Analysis Method in RCC-MR

  • Koo, Gyeong-Hoi;Bong Yoo
    • Nuclear Engineering and Technology
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    • v.33 no.6
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    • pp.566-584
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    • 2001
  • In this paper, the progressive deformation and the creep-fatigue damage for the conceptually designed reactor internals of KALIMER(Korea Advanced Liquid MEtal Reactor) are carried out by using the elastic analysis method in the RCC-MR code for normal operating conditions including the thermal load, seismic load (OBE) and dead weight. The maximum operating temperature of this reactor is 53$0^{\circ}C$ and the total service lifetime is 30 years. Thus, the time- dependent creep and stress-rupture effects become quite important in the structural design. The effects of the thermal induced membrane stress on the creep-fatigue damage are investigated with the risk of the elastic follow-up. To calculate the thermal stress, detailed thermal analyses considering conduction, convection and radiation heat transfer mechanisms are carried out with the ANSYS program. Using the results of the elastic analysis, the progressive deformation and creep-fatigue damages are calculated step by step using the RCC-MR in detail. This paper ill be a very useful guide for an actual application of the high temperature structural design of the nuclear power plant accounting for the time-dependent creep and stress-rupture effects.

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Study on Core Debris Recriticality During Hypothetical Severe Accidents in Three Element Core Design of The Advanced Neutron Source Reactor

  • Shin, Sung-Tack
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.05b
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    • pp.467-472
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    • 1996
  • This study discusses special aspects of severe accident related recriticality modeling and analysis in the Advanced Neutron Source (ANS) reactor.$^{1, 2)}$ The analytical comparison of three elements core to former two elements case is conducted including evaluation of suitable nuclear cross-section sets to account for the effects of system configulation, fuel and moderator mixture temperature, material dispersion and the other thermal-hydraulics. Three elements core ANS reactor is the alternative core design which was proposed as a modified core design, with three fuel elements instead of two, that would allow operation with only 50% enriched uranium (former uranium fuel is the baseline design value of 93%) A comprehensive test matrix of calculations to evaluate the threat of a criticality event in the ANS is described. Strong dependencies still on geometry, material constituents, and thermal-hydraulic conditions are verified. Therefore, the concepts of mitigative design features are qualified.d.

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An Investigation of Thermal Margin for External Reactor Vessel Cooling(ERVC) in Large Advanced Light Water Reactors(ALWR)

  • Park, Jong-Woon;Jerng, Dong-Wook
    • Proceedings of the Korean Nuclear Society Conference
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    • 1997.05a
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    • pp.473-478
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    • 1997
  • A severe accident management strategy, in-vessel retention corium through external reactor vessel cooling(ERVC) is being studied worldwide as a means to prevent reactor vessel failure following a core melt accident. An evaluation of feasibility of this ERVC for a large Advanced Light Water Reactor (ALWR) is presented. To account for the coolability of corium and metal in the reactor vessel, a thermal analysis is performed using an existing method. Results show that the peak heat flux along the inner surface of the reactor vessel lower head has a relatively smaller margin than a small capacity reactor such as AP600 in regards with the critical heat flux attainable at the outer surface of the reactor vessel lower head.

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Moving Mesh Application for Thermal-Hydraulic Analysis in Cable-In-Conduit-Conductors of KSTAR Superconducting Magnet

  • Yoon, Cheon-Seog;Qiuliang Wang;Kim, Keeman;Jinliang He
    • Journal of Mechanical Science and Technology
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    • v.16 no.4
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    • pp.522-531
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    • 2002
  • In order to study the thermal-hydraulic behavior of the cable-in-conduit-conductor (CICC), a numerical model has been developed. In the model, the high heat transfer approximation between superconducting strands and supercritical helium is adopted. The strong coupling of heat transfer at the front of normal zone generates a contact discontinuity in temperature and density. In order to obtain the converged numerical solutions, a moving mesh method is used to capture the contact discontinuity in the short front region of the normal zone. The coupled equation is solved using the finite element method with the artificial viscosity term. Details of the numerical implementation are discussed and the validation of the code is performed for comparison of the results with thse of GANDALF and QSAIT.

Thermal Decomposition of Octanethiolate Self-Assembled Monolayers on Cu(111) in UHV

  • Sung, Myung-M.;Yun, Won-J.;Lee, Sun-S.;Kim, Yun-Soo
    • Bulletin of the Korean Chemical Society
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    • v.24 no.5
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    • pp.610-612
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    • 2003
  • Octanethiol ($CH_3(CH_2)_7SH$) based self-assembled monolayer on Cu(111) in ultra-high vacuum has been examined using x-ray photoelectron spectroscopy (XPS), temperature programmed desorption (TPD), intergrated desorption mass spectrometry (IDMS), and contact angle analysis. The results show that the octanethiolate monolayers similar to those on gold are formed on Cu(111). The monolayers are stable up to temperatures of about 480 K. Above 495 K the monolayers decompose via the γ-hydrogen elimination mechanism to yield 1-octene in the gas phase. The thiolate head groups on the copper surface change to Cu₂S following the decomposition of hydrocarbon fragments in the monolayers at about 605 K.