• Title/Summary/Keyword: critical heat flux

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Superconducting Properties of Large Single Grain Gd1.5Ba2Cu3O7-y Bulk Superconductors (대면적 단결정 Gd1.5Ba2Cu3O7-y 벌크 초전도체의 초전도 특성)

  • Kim, Chan-Joong;Park, Seung Yeon;Kim, Kwang-Mo;Park, Soon-Dong;Jun, Byung-Hyuk
    • Korean Journal of Materials Research
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    • v.22 no.11
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    • pp.569-574
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    • 2012
  • Large single grain $Gd_{1.5}Ba_2Cu_3O_{7-y}$ (Gd1.5) bulk superconductors were fabricated by a top-seeded melt growth (TSMG) process using an $NdBa_2Cu_3O_{7-y}$ seed. The seeded Gd1.5 powder compacts with a diameter of 50 mm were subjected to the heating cycles of a TSMG process. After the TSMG process, the diameter of the single grain Gd1.5 compact was reduced to 43 mm owing to the volume contraction during the heat treatment. The superconducting transition temperature ($T_c$) of the top surface of the single grain Gd1.5 sample was as high as 93.5 K. The critical current densities ($J_cs$) at 77 K and 1T and 1.5 T were in ranges of 25,200-43,900 $A/cm^2$ and 10,000-23,000 $A/cm^2$, respectively. The maximum attractive force at 77 K of the sample field-cooled using an Nd-B-Fe permanent magnet (surface magnetic field of 0. 527 T) was 108.3 N; the maximum repulsive force of the zero field-cooled sample was 262 N. The magnetic flux density of the sample field-cooled at 77 K was 0.311T, which is approximately 85% of the applied magnetic field of 0.375 T. Microstructure investigation showed that many $Gd_2BaCuO_5$ (Gd211) particles of a few ${\mu}m$ in size, which are flux pinning sites of Gd123, were trapped within the $GdBa_2Cu_3O_{7-y}$ (Gd123) grain; unreacted $Ba_3Cu_5O_8$ liquid and Gd211 particles were present near the edge regions of the single grain Gd1.5 bulk compact.

Field Loss Analysis and Cooling Analysis of HTS Synchronous Motor (고온초전도 동기모터의 계자손실 해석 및 냉각 해석)

  • Kim, Ki-Chan;Lee, Dae-Dong
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.19 no.3
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    • pp.69-74
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    • 2018
  • Large industrial motors require a large area because of the high risk of shutdown accidents and large industrial accidents due to the lowering of the dielectric strength of the armature windings and overheating problems. Therefore, there is a demand for a large-capacity motor that has small size, light weight, and excellent dielectric strength compared with conventional motors. Superconducting motors have advantages of high efficiency and output power, low size, low weight, and improved stability. This results from greatly increasing the magnetic field generation by using superconductive field coils in rotating machines such as generators and motors. It is very important to design and analyze the cooling system to lower the critical temperature of the wires to achieve superconducting performance. In this study, a field loss analysis and low-temperature heat transfer analysis of the cooling system were performed through the conceptual design of a 100-HP high-temperature superconducting synchronous motor. The field loss analysis shows that a uniform pore magnetic flux density appears when high-temperature superconducting wire is used. The low-temperature heat transfer analysis for gaseous neon and liquid neon showed that a flow rate of 1 kg/min of liquid neon is suitable for maintaining low-temperature stability of the high-temperature superconducting wire.

Measurements of Wet Canopy Evaporation in Forests: A Review (산림에서의 젖은 군락 증발 관측: 고찰)

  • Kwon, Hyo-Jung
    • Korean Journal of Agricultural and Forest Meteorology
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    • v.13 no.2
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    • pp.56-68
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    • 2011
  • Wet canopy evaporation ($E_{WC}$) has been recognized as a significant component of total evapotranspiration, especially in forests and therefore it is critical to accurately assess $E_{WC}$ to understand forest hydrological cycle. In this review, I focused on the measurement methods and evaluating the magnitudes of $E_{WC}$ at diverse forest types (e.g., deciduous, coniferous, mixed, and rain forests). I also present the general issues to be considered for $E_{WC}$ measurements. The commonly used measurement methods for $E_{WC}$ include the water balance, energy balance, and the Penman-Monteith (PM) methods. The magnitudes of $E_{WC}$ ranged from 5 to 54% of precipitation based on the literature review, showing a large variation even for a similar forest type possibly related to canopy structure, rainfall intensity, and other meteorological conditions. Therefore, it is difficult to draw a general conclusion on the contribution of $E_{WC}$ to evapotranspiration from a particular forest type. Errors can arise from the measurements of precipitation (due to varying wind effect) and throughfall (due to spatial variability caused by canopy structure) for water balance method, the measurements of sensible heat flux and heat storage for energy balance method, and the estimation of aerodynamic conductance and unaccounted sensible heat advection for the PM method. For a reliable estimation of $E_{WC}$, the combination of ecohydrological and micrometeorological methods is recommended.

Contribution of thermal-hydraulic validation tests to the standard design approval of SMART

  • Park, Hyun-Sik;Kwon, Tae-Soon;Moon, Sang-Ki;Cho, Seok;Euh, Dong-Jin;Yi, Sung-Jae
    • Nuclear Engineering and Technology
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    • v.49 no.7
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    • pp.1537-1546
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    • 2017
  • Many thermal-hydraulic tests have been conducted at the Korea Atomic Energy Research Institute for verification of the SMART (System-integrated Modular Advanced ReacTor) design, the standard design approval of which was issued by the Korean regulatory body. In this paper, the contributions of these tests to the standard design approval of SMART are discussed. First, an integral effect test facility named VISTA-ITL (Experimental Verification by Integral Simulation of Transients and Accidents-Integral Test Loop) has been utilized to assess the TASS/SMR-S (Transient and Set-point Simulation/Small and Medium) safety analysis code and confirm its conservatism, to support standard design approval, and to construct a database for the SMART design optimization. In addition, many separate effect tests have been performed. The reactor internal flow test has been conducted using the SCOP (SMART COre flow distribution and Pressure drop test) facility to evaluate the reactor internal flow and pressure distributions. An ECC (Emergency Core Coolant) performance test has been carried out using the SWAT (SMART ECC Water Asymmetric Two-phase choking test) facility to evaluate the safety injection performance and to validate the thermal-hydraulic model used in the safety analysis code. The Freon CHF (Critical Heat Flux) test has been performed using the FTHEL (Freon Thermal Hydraulic Experimental Loop) facility to construct a database from the $5{\times}5$ rod bundle Freon CHF tests and to evaluate the DNBR (Departure from Nucleate Boiling Ratio) model in the safety analysis and core design codes. These test results were used for standard design approval of SMART to verify its design bases, design tools, and analysis methodology.

A Sensitivity Study of a Steam Generator Tube Rupture for the SMART-P (SMART 연구로의 증기발생기 전열관 파열사고 민감도 분석)

  • Kim Hee-Kyung;Chung Young-Jong;Yang Soo-Hyung;Kim Hee-Cheol;Zee Sung Quun
    • Journal of the Korean Society of Safety
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    • v.20 no.2 s.70
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    • pp.32-37
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    • 2005
  • The purpose of this study is for the sensitivity study f9r a Steam Generator Tube Rupture (SGTR) of the System-integrated Modular Advanced ReacTor for a Pilot (SMART-P) plant. The thermal hydraulic analysis of a SGIR for the Limiting Conditions for Operation (LCO) is performed using TASS/SMR code. The TASS/SMR code can calculate the core power, pressure, flow, temperature and other values of the primary and secondary system for the various initiating conditions. The major concern of this sensitivity study is not the minimum Critical Heat Flux Ratio(CHFR) but the maximum leakage amount from the primary to secondary sides at the steam generator. Therefore the break area causing the maximum accumulated break flow is researched for this reason. In the case of a SGIR for the SMART-p, the total integrated break flow is 11,740kg in the worst case scenario, the minimum CHFR is maintained at Over 1.3 and the hottest fuel rod temperature is below 606"I during the transient. It means that the integrity of the fuel rod is guaranteed. The reactor coolant system and the secondary system pressures are maintained below 18.7MPa, which is system design pressure.

A Study on Evaluation Methods for the Fire-retardant Performance of Hanok Components (건축 마감재의 화재안전기준 비교분석을 통한 한옥 부재의 난연성능 평가기준 연구)

  • Kwark, Ji-Hyun;Choi, Jung-Min;Ku, Jae-Hyun
    • Fire Science and Engineering
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    • v.25 no.5
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    • pp.1-7
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    • 2011
  • In this study, standards and test methods for building materials of domestic and foreign countries were compared and analyzed to propose evaluation methods for the fire-retardant performance of HANOK components (Traditional house). IBC and NFPA codes recently have been adopted in the US, and the properties such as critical heat flux, fire spread index and smoke density are being used as an evaluation reference. In Europe, the unified Euroclass has been adopted and the surface flammability, prototype fire test or cone calorimeter test are conducted for the performance test. Japan has the similar system as Korea where the class is classified into 3 grades. We tried to study a quantitative evaluation method of fire retardant performance for the HANOK components based on the analysis results of the several countries' standards and test methods for building materials.

Fire test procedures for flammability of bulkhead, ceiling and deck finish materials (선박의 격벽, 천정, 내장재 및 표면바닥재의 화재안정성 평가방법)

  • Kim, S.Y.;Kim, D.S.;Ahn, B.H.;Kwark, J.H.
    • Proceedings of the Korea Institute of Fire Science and Engineering Conference
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    • 2008.04a
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    • pp.117-119
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    • 2008
  • It is very important to protect life, property at sea from any fire. Recommendation on improved fire test procedures for surface flammability of bulkhead, ceiling and deck finish materials specifies a procedure for measuring fire characterizing their flammability and thus their suitability for use in marine construction. In this paper, we investigated the positive expected by fire test procedures for flammability of bulkhead, ceiling and deck finish materials. Also, unusual materials were analyzed. Finally, we suggest methods to solve several problems related to unusual materials.

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Computer Simulation for Smelting Tretment of Waste Casting Sand (폐주물사의 용융처리에 관한 Computer Simulation)

  • Chung, Won-Sub;Min, Dong-Jun;Kim, Yong-Ha
    • Resources Recycling
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    • v.5 no.3
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    • pp.24-30
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    • 1996
  • The computcr s~mulatiun model in vanaus s~nelllng process for melling waste cashhg sand was developed by using energy and malcrial balance concept. This modcl can prcdict the coal, flux and oxygen conaumptron and thc volume and temperature of off-gas The ~niljor critical varlablcs for smclting process can be crplained by using the analysis of energy and malc~ialb alance. Thc Innst lmportarlt variables lor smelting process were h i ~ hpo st-combust~anr atla, high heat transfer crficiency and refractory pratcclion lechnalogy. For saving encrg), in this smelting proccss, selection of caw marerials i.e coal, flus was important, cspacially ubi~go f low volatile coal was prufitahle.

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An Experimental Study of the Pool-Boiling CHF on Downward-Facing Plates (하향 평판에서의 풀비등 임계열유속에 관한 실험적 연구)

  • Yang, Soo-Hyung;Baek, Won-Pil;Chang, Soon-Heung
    • Nuclear Engineering and Technology
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    • v.26 no.4
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    • pp.493-501
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    • 1994
  • An experimental study has been peformed on the pool-boiling critical heat flux (CHF) phenomenon on downward -facing plates. The CHF for inclinations of -90$^{\circ}$(horizontally downward position), -88$^{\circ}$, -86$^{\circ}$, -84$^{\circ}$, -60$^{\circ}$ and -40$^{\circ}$ were measured using plate-type test sections of 20mm 200mm and 25mm 200mm in a pool of saturated water under atmospheric pressure. The measured CHF was lower for the wider test section and decreased as its orientation approached to the horizontally downward position. The lower CHF can be attributable to the increased difficulty for the bubbles in escaping from the heater surface. When compared with the previous works, the overall trends were similar; however, a transition angle, at which the decrease rate in the CHF was changed, was observed in the vicinity of -80$^{\circ}$.

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Applicability research of round tube CHF mechanistic model in rod bundle channel

  • Liu, Wei;Peng, Shinian;Shan, Jianqiang;Jiang, Guangming;Liu, Yu;Deng, Jian;Hu, Ying
    • Nuclear Engineering and Technology
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    • v.53 no.2
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    • pp.439-445
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    • 2021
  • In view of the complex geometric structure of the rod bundle channel and the limitation of the current CHF visualization experiment technology, it is very difficult to obtain the rod bundle CHF mechanism directly through the phenomenon of the rod bundle CHF visualization experiment. In order to obtain the applicable CHF mechanism assumption for rod bundle channel, firstly, five most representative DNB type round tube CHF mechanistic models are obtained with evaluation and screening. Then these original round tube CHF mechanistic models based on inlet conditions are converted to local conditions and coupled with subchannel analysis code ATHAS. Based on 5 × 5 full-length rod bundle CHF experimental data independently developed by Nuclear Power Institute of China (NPIC), the applicability research of each model for CHF prediction performance in rod bundle channel is carried out, and the commonness and difference of each model are comparatively studied. The CHF mechanism assumption of superheated liquid layer depletion that is most likely to be applicable for the rod bundle channel is selected and two directions that need to be improved are given. This study provides a reference for the development of CHF mechanistic model in rod bundle channel.