• Title/Summary/Keyword: heat of fusion

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Analysis of Heat Flow and Thermal Stress for Divertors (디버터의 열유동 및 열응력 해석 1)

  • Lee, Sang-Yun;Kim, Hong-Bae
    • Journal of the Korean Society for Precision Engineering
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    • v.16 no.1 s.94
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    • pp.238-245
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    • 1999
  • For the optimal design of plasma facing components of a fusion reactor, thorough understanding of thermal behavior of high heat. nux components are required. The purpose of this research is to investigate the characteristics of heat flow and thermal stress in divertors which are exposed to high heat load varing with time and space-Numerical simulations of heat now and thermal stress for three types of diverter are performed using finite volume method and finite element method. Respectly, commercial FLUENT code are used in the heat flow simulation, and maximum surface temperature, temperature distribution and cooling rate are calculated. Commercial ABQUS code are used for calculating temperature distribution. thermal stress, strain and displacement. Through this computer simulation. design data for cooling system and Structural provided.

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Study of Chip-level Liquid Cooling for High-heat-flux Devices (고열유속 소자를 위한 칩 레벨 액체 냉각 연구)

  • Park, Manseok;Kim, Sungdong;Kim, Sarah Eunkyung
    • Journal of the Microelectronics and Packaging Society
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    • v.22 no.2
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    • pp.27-31
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    • 2015
  • Thermal management becomes a key technology as the power density of high performance and high density devices increases. Conventional heat sink or TIM methods will be limited to resolve thermal problems of next-generation IC devices. Recently, to increase heat flux through high powered IC devices liquid cooling system has been actively studied. In this study a chip-level liquid cooling system with TSV and microchannel was fabricated on Si wafer using DRIE process and analyzed the cooling characteristics. Three different TSV shapes were fabricated and the effect of TSV shapes was analyzed. The shape of liquid flowing through microchannel was observed by fluorescence microscope. The temperature differential of liquid cooling system was measured by IR microscope from RT to $300^{\circ}C$.

Failure analysis of damaged tungsten monoblock components of upper divertor outer target in EAST fusion device

  • Kang Wang;Ya Xi;Xiang Zan;Dahuan Zhu;Laima Luo;Rui Ding;Yucheng Wu
    • Nuclear Engineering and Technology
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    • v.56 no.6
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    • pp.2307-2316
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    • 2024
  • A melting failure of W monoblock components of the upper divertor outer target in EAST occurred during the plasma campaigns in 2019. The failure characters and microstructure evolution of the failed W monoblock have been well investigated on one string (W436 string). Near the strike point region where heat flux density is highest, macroscopic cracks and severe surface damage such as dimensional change, melting and solidification are visible in several W monoblocks. At the same time, debonding, melting and migration of Cu/CuCrZr cooling tube components introduced fatal damage to the structure and function. The heat-induced microstructure evolution in the rest part has been examined via hardness tests and metallography. From the heat flux surface to the cooling tube, hardness increased gradually and the recrystallized grains could be found in the region with the highest temperature, while recrystallization grains also appear in some W monoblocks near the cooling tube area. The detailed microstructure has been investigated by metallography and EBSD. Such cases in EAST provide experiences on the extreme condition of accidental loss of coolant or higher discharge power in future devices.

Effect of stress relief heat treatment on the residual stress and hardness of additively manufactured Ti-6Al-4V alloy (응력제거 열처리 공정조건이 적층제조한 Ti-6Al-4V 합금의 잔류응력 및 경도에 미치는 영향)

  • Yeonghwan Song
    • Journal of the Korean Crystal Growth and Crystal Technology
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    • v.33 no.6
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    • pp.282-287
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    • 2023
  • The effect of stress relief heat treatment temperature and duration time on the microstructure, residual stress and Vickers hardness of additively manufactured Ti-6Al-4V alloy using laser powder bed fusion process was clarified. As a result of stress relief heat treatment for 240 minutes at 823 K and 60 minutes or more at 873 K, residual stress was decreased less than 30 MPa without grain growth and phase transformation which causes dimensional distortion and deterioration of mechanical properties. In addition, hardness was increased with increasing heat treatment temperature and duration time. It was deduced that the refinement of acicular martensitic α' phase due to the increasing duration time of isothermal heat treatment at 773~873 K, which was not detected by XRD and phase map analysis using SEM-EBSD, probably increases the hardness.

Change of Mechanical Properties of Clad Steel According to the Welding Process Design (용접 공정 디자인에 따른 클래드강의 기계적 성질 변화)

  • Lee, Jung-Hyun;Park, Jaw-Won
    • Journal of the Korean Society of Manufacturing Technology Engineers
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    • v.22 no.3
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    • pp.372-379
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    • 2013
  • In this study, we investigated the traits of the clad metals used in hot-rolled clad steel plates. We examined the sensitization and mechanical properties of STS 316 steel plate and carbon steel (A516) under the specific circumstances of post heat treatment and whether a weld was multilayered and thick or repeated because of repairs. The test conditions were as follows. The clad steel plates were butt-welded using FCAW/SAW, and the heat treatment was conducted at $625^{\circ}C$, for 80, 160, 320, 640, or 1280 min. The change in the corrosion resistance was evaluated in these specimens. In the case of the carbon steel (A516), as the heat treatment time increased, the annealing effect caused the tensile strength to decrease. The micro- hardness gradually increased and then decreased after 640 min. The elongation and contraction of the area increased gradually. An oxalic acid etch test and EPR test on STS316, a clad metal, showed a STEP structure and no sensitization. From the test results for the multi-layered and repair welds, it could be concluded that there is no effect on the corrosion resistance of clad metals. In summary, the purpose of this study was to suggest some considerations when developing on-site techniques and evaluate the sensitization of stainless steels.

EMC/LVD Compatibility Evaluation of ITER AC/DC Converter Subrack by EN 61000 and IEC 61010 (ITER AC/DC Converter 서브랙의 EN 61000 및 IEC 61010에 의한 EMC/LVD 시험평가)

  • Shin, Hyun-Kook;Oh, Jong-Seok;Song, In-Ho;Suh, Jae-Hak;Choi, Jung-Wan
    • The Transactions of the Korean Institute of Power Electronics
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    • v.26 no.3
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    • pp.222-226
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    • 2021
  • To comply with CE marking requirements, the electromagnetic compatibility (EMC) and low-voltage directive (LVD) tests are conducted on the sub-racks of International Thermonuclear Experimental Reactor (ITER) AC/DC converters and bypass switches. The EMC tests consist of a series of tests, including the electromagnetic interference test, the electromagnetic field immunity test, and the rapid transient burst immunity test. In the LVD test, the electric shock protection test, the xcessive temperature limit and heat resistance of equipment tests, and the fire spread prevention test are performed. This work presents and reviews the European Directive for EMC/LVD and introduces the methods of EMC and LVD tests for the sub-racks of AC/DC converters and bypass switches. It also evaluates the test method and results to meet the European Directive requirements for CE marking. The sub-racks of ITER AC/DC converters and bypass switches successfully pass the EMC and LVD tests.

Conceptual Design of High-Tc Superconducting Current leads for Superconducting Nuclear Fusion Magnets with respect to various HTS tapes (HTS 선재에 따른 초전도 핵융합 마그넷용 고온초전도 전류도입선의 개념설계)

  • Jang, J.Y.;Chang, K.S.;Kim, Y.J.;Choi, S.J.;Jo, H.C.;Chu, S.Y.;Ko, T.K.
    • Progress in Superconductivity and Cryogenics
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    • v.12 no.1
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    • pp.32-36
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    • 2010
  • Superconducting current leads are indispensible for reducing power loss when subjecting current into superconducting magnets. HTS(High-Tc superconducting) current leads are divided into two types; one is bulk type and the other is tape type. In this paper, conceptual design on the HTS current leads which adopts tape type for nuclear fusion magnets is carried out using magnetic field analysis and thermal analysis. When large current flows through superconducting current leads, strong self magnetic field is generated and applied to the superconducting tapes. This phenomenon leads to the critical current decrease of the superconducting tape. Therefore, we analyzed magnetic field distribution of current leads and found the proper arrangement with respect to the various HTS tapes. In addition to the magnetic field analysis, heat leak through the current leads was also calculated to know which HTS tape is superior than others in thermal aspect. Magnetical field analysis and calculation of heat leak are performed to design 2 kA class HTS current leads.

Characteristics of High Heat Input Welding (대입열용접 특성)

  • Kim, Hee-Jin;Ryu, H.S.
    • Proceedings of the KWS Conference
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    • 2010.05a
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    • pp.13-17
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    • 2010
  • 용접입열 (heat input)은 용접시에 외부로부터 가해지는 열량으로 정의되기 때문에, 대입열용접은 용접입열량이 높은 용접이라고 정의할 수 있다. 통상적으로는 기존에 사용하던 용접기법보다 입열량이 높은 경우에 이를 대입열 용접기법이라고 부르게 되는데, 최근에는 편면 SAW 및 EGW기법 등이 대입열 용접기법으로 통칭되고 있다. 이들 기법의 공통된 특징은 one-pass 용접이라는 것과 용접열영향부에서의 열전달이 2차원적이라는 것이다. 본 연구에서는 Rosenthal의 해석식을 이용하여 이들 두 기법의 열전달 특성을 fusion line 위치에서 분석하여 보았는데, 두께에 따른 열전달 특성에 있어서 커다란 차이를 보여 주게 됨을 확인하였다. 편면 SAW에서는 열이력이 두께의 영향을 받아 두께(입열)가 증가함에 따라 고온에서의 유지시간은 증가하고 냉각속도는 느려지게 된다. 그러나 EGW에서는 입열과 두께가 일차함수적인 관계를 가지고 있기 때문에 열이력에 미치는 두께(입열)의 영향이 없다는 결과가 도출되었다. 이러한 차이로 인하여 편면 SAW에서는 강판 두께가 증가함에 따라 fusion line에서의 충격인성은 저하할 것으로 예상되는 반면에 EGW에서는 두께의 영향을 받지 않을 것으로 예상되었다. 그럼으로 EGW용 대입열용접용 강재의 '대입열 용접성'을 정량적으로 평가할 목적으로 '적용 가능한 최대입열 수준' 또는 '적용 가능한 최대 강판두께' 등으로 평가하는 것은 의미가 없는 것이다. 단지 강판의 두께에 따라 강재의 화학조성이나 제조공정에 있어 차이가 있다면, 이로 인한 'EGW 용접성'의 차이는 있을 수 있다.

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Hydraulic Behaviors of KSTAR PF Coils in Operation

  • Park, S.H.;Chu, Y.;Kim, Y.O.;Yonekawa, H.;Chang, Y.B.;Woo, I.S.;Lee, H.J.;Park, K.R.
    • Progress in Superconductivity and Cryogenics
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    • v.14 no.2
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    • pp.24-27
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    • 2012
  • The superconducting coil system is one of the most important components in Korea Superconducting Tokamak Advanced Research (KSTAR), which has been operated since 2008. $Nb_3Sn$ and NbTi superconductors are being used for cable-in-conduit conductors (CICCs) of the KSTAR toroidal field (TF) and poloidal field (PF) coils. The CICCs are cooled by forced-flow supercritical helium about 4.5 K. The temperature, pressure and mass flow rate of the supercritical helium in the CICCs are interacting with each other during the operation of the coils. The complicate behaviors of the supercritical helium have an effect on the operation and the efficiency of the helium refrigeration system (HRS) by means of, for instance, pressure drop. The hydraulic characteristics of the supercritical helium have been monitored while the TF coils have stably achieved the full current of 35 kA. In other hands, the PF coils have been operated with various pulsed or bipolar mode, so the drastic changes happen in view of hydraulics. The heat load including AC loss on the coils has been analyzed according to the measurement. These activities are important to estimate the temperature margin in various PF operation conditions. In this paper, the latest hydraulic behaviors of PF coils during KSTAR operation are presented.

ANALYSIS OF WELD METAL STRUCTURE AND MECHANICAL BEHAVIOUR ENVISAGING PHASE CHANCE LATENT HEAT EFFECT

  • Rajesh S.R.;Bang Han Sur;Joo Sung Min;Bang Hee Sun
    • Proceedings of the KWS Conference
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    • v.43
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    • pp.283-285
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    • 2004
  • In this paper an important class of problems in welding which come under the category of phase change is considered, Solidification and melting are important process in welding field. Phase change problems are accompanied by either absorption or release of thermal energy i,e, heat transfer process. This is complicated by the release or absorption of the latent heat of fusion at the solid-liquid interface. In this study the liberation of latent heat is taken in to account using fixed grid method. The numerical simulation and the finite element codes for the heat transfer analysis including the latent heat term has been developed based on this fixed grid method.

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