• Title/Summary/Keyword: Thermal Event

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Retrieval of Thermal Tropopause Height using Temperature Profile Derived from AMSU-A of Aqua Satellite and its Application (Aqua 위성 AMSU-A 고도별 온도자료를 이용한 열적 대류권계면 고도 산출 및 활용)

  • Cho, Young-Jun;Shin, Dong-Bin;Kwon, Tae-Yong;Ha, Jong-Chul;Cho, Chun-Ho
    • Atmosphere
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    • v.24 no.4
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    • pp.523-532
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    • 2014
  • In this study, thermal tropopause height defined from WMO (World Meteorological Organization) using temperature profile derived from Advance Microwave Sounding Unit-A (AMSU-A; hereafter named AMSU) onboard EOS (Earth Observing System) Aqua satellite is retrieved. The temperature profile of AMSU was validated by comparison with the radiosonde data observed at Osan weather station. The validation in the upper atmosphere from 500 to 100 hPa pressure level showed that correlation coefficients were in the range of 0.85~0.97 and the bias was less than 1 K with Root Mean Square Error (RMSE) of ~3 K. Thermal tropopause height was retrieved by using AMSU temperature profile. The bias and RMSE were found to be -5~ -37 hPa and 45~67 hPa, respectively. Correlation coefficients were in the range of 0.5 to 0.7. We also analyzed the change of tropopause height and temperature in middle troposphere in the extreme heavy rain event (23 October, 2003) associated with tropopause folding. As a result, the distinct descent of tropopause height and temperature decrease of ~8 K at 500 hPa altitude were observed at the hour that maximum precipitation and maximum wind speed occurred. These results were consistent with ERA (ECMWF Reanalysis)-Interim data (potential vorticity, temperature) in time and space.

Thermal Design of Electronic for Controlling X-band Antenna of Compact Advanced Satellite (차세대 중형위성 탑재 X-밴드 안테나 구동용 전자유닛 APD 열설계 및 열해석)

  • Kim, Hye-In;You, Chang-Mok;Kang, Eun-Su;Oh, Hyun-Ung
    • Journal of Aerospace System Engineering
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    • v.12 no.1
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    • pp.57-67
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    • 2018
  • The APD (Antenna Pointing Driver) is an electronic equipment tool that is used to drive the two-axis gimbal-type antenna for the image data transmission of CAS (Compact Advanced Satellite). In this study, a heat dissipation of EEE (Electrical, Electronic and Electromechanical) is reviewed, to identify the parts that directly affected its efficiency, lifetime as well as the reliability of the structure. This event eventually incurs a failure of the EEE part itself, or even the entire satellite system as noted in experiments in this case. To guarantee reliability of electronic equipment during the mission, the junction temperature of EEE parts is considered a significant and important design factor, and subsequently must be secured within the allowable range. Therefore, the notation of the thermal analysis considering the derating is indispensable, and a proper thermal mathematical model should be constructed for this case. In this study, the thermal design and thermal analysis are performed to confirm the temperature requirement of the APD. In addition, we noted that the validity of the thermal model, according to each of the identified modeling methods, was therefore compared through the thermal analysis utilized in this case.

Integrity evaluation of Kori 1 reactor vessel for Rancho Seco transient (Rancho Seco Transient에 대한 고리 1호기 원자로용기의 건전성 평가)

  • Jhung, M.J;Park, Y.W;Lee, J.B
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.21 no.7
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    • pp.1089-1096
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    • 1997
  • In this paper, Rancho Seco transient which is reported as a typical pressurized thermal shock event is postulated to be occuring in the Kori unit 1 plant, the oldest nuclear power plant in Korea. For the given material properties, transient history such as temperature and pressure, and postulated flaw, the stress distribution is obtained to calculate stress intensities for a wide range of assumed crack sizes. The stress intensities are compared with the fracture toughness, which is determined using the material properties and the distribution of the nil ductility transition temperature, to determine if cracking is expected to occur during the transient. The allowable operating year for the transient is determined and the evaluation results are discussed.

Fracture Analysis of Plasma Spray Coating by Classification of AE Signals (AE파형분류에 의한 용사코팅재의 파손해석)

  • Kim, G.S.;Park, K.S.;Hong, Y.U.
    • Journal of Power System Engineering
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    • v.6 no.3
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    • pp.24-30
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    • 2002
  • The deformation and fracture behaviors of both Al2O3 and Ni 4.5wt.%Al plasma thermal spray coating were investigated by an acoustic emission method. Plasma thermal spray coating is formed by a process in which melted particles flying with high speed towards substrate, then crash and spread on the substrate surface cooled and solidified in a very short time, stacking of the particles makes coating. A tensile test is conducted on notch specimens in a stress range below the elastic limit of substrate. A bendind test is done on smooth specimens. The waveforms of AE generated from the both test coating specimens can be classified by FFT analysis into two types which low frequency(type I) and high frequency(type II). The type I waveform is considered to corresponds exfoliation of coating layers and type II waveform corresponds the plastic deformation of notch tip. The fracture of the coating layers can estimate by AE event and amplitude, because AE features increase when the deformation generates.

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A Study on the Reliability Improvement of the Turbine Control Valve System in Nuclear and Thermal Power Plants (원자력/화력발전소의 터빈제어밸브시스템의 신뢰성 향상에 관한 연구)

  • Yang, Jong Dae;Yang, Seok Jo;Lee, Yong Bum
    • Journal of Drive and Control
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    • v.16 no.4
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    • pp.93-100
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    • 2019
  • Nuclear and thermal power plants must provide the turbines with an appropriate degree of high temperature and high pressure steam, to produce the optimum electricity. Additionally, in the event of system and power system failure during electrical production, the steam is immediately disabled, to protect the turbines and generators rotating at high speed. The plant thus uses a special steam control valve system for turbine control, which is opened by force of the hydraulic servo actuator and closed by a large steel spring force. In this study, the causes of failure of the turbine control valve system, a key device of the power plants, were analyzed, and the causes of failure were improved relative to reliability of the equipment.

The Effect of Rainfall on the Water Quality of a Small Reservoir (Lake Wangkung, Korea)

  • Hwang, Gil-Son;Kim, Jae-Ok;Kim, Jai-Ku;Kim, Young-Chul;Kim, Bom-Chul
    • Korean Journal of Ecology and Environment
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    • v.38 no.spc
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    • pp.39-43
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    • 2005
  • The dynamics of water quality with the storm events were analyzed in a small reservoir for irrigation, Lake Wangkung. Water quality of the inflowing stream fluctuated seasonally with the variation of flow rate. Thermal stratification was consistent from April to October below 2 m depths and anoxic layer was developed below 2 m depth in summer. The unique feature of temperature showed that thermal stratification was disrupted by a heavy rain event during monsoon, but hypolimnetic hypoxia were reestablished after a few days. Phosphorus and nitrogen increased immediately following storm events. The marked increase may be due to the input of P-rich storm runoff from the watershed. Internal phosphorus loading can be one of the explanations for TP increases in summer. When there was a storm, total populations of phytoplankton and zooplankton was reduced immediately following the storm, indicating possible flushing of algae and zooplankton. After a lag period of low-density the plankton population bloomed to a peak again within five days after the storm. Turbid water in lake became clear again which coincided with the time of the phytoplankton buildup. The results demonstrate that water quality is regulated greatly by rainfall intensity in Lake Wangkung.

Space Physics Sensor on KOMPSAT-1

  • Min, Kyoung-Wook;Choi, Young-Wan;Shin, Young-Hoon;Lee, Jae-Jin;Lee, Dae-Hee;Kim, Jhoon
    • Proceedings of the KSRS Conference
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    • 1998.09a
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    • pp.355-360
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    • 1998
  • A small package of plasma instruments, Space Physics Sensor, will monitor the space environment and its effects on microelectronics in the low altitude region as it operates on board the KOMPSAT-1 from 1999 over the maximum of the solar cycle 23. The Space Physics Sensor (SPS) consists of two parts: the Ionospheric Measurement Sensor (IMS) and the High Energy Particle Detector (HEPD). IMS will make in situ Measurements of the thermal electron density and temperature, and is expected to provide a global map of the thermal electron characteristics and the variability according to the solar and geomagnetic activity in the high altitude ionosphere of the KOMPSAT-t orbit. HEPD will measure the fluxes of high energy protons and electrons, monitor the single event upsets caused by these energetic charged particles, and give the information of the total radiation dose received by the spacecraft. The continuous operation of these sensors, along with the ground measurements such as incoherent scatter radars, digital ionosondes and other spacecraft measurements, will enhance our understanding of this important region of practical use for the low earth orbit satellites.

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Analysis of Chemistry Factor and RTPTS Margin for Domestic Reactor Pressure Vessel Materials by using the Surveillance Data (감시시험 결과를 이용한 국내원전 압력용기 재료의 Chemistry Factor 및 RTPTS 평가여유도 분석)

  • Lee, Ho-Jin;Yoon, Ji-Hyun;Choi, Kwon-Jae;Lee, Bong-Sang
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.7 no.3
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    • pp.15-22
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    • 2011
  • The chemistry factor and RTPTS margin for domestic reactor pressure vessel materials were analyzed by using the surveillance data which have been obtained from 8 nuclear power plants in Korea. The surveillance data have been used to assess the integrity of the pressure vessel under the pressurized thermal shock (PTS) event. The chemistry factor, which is determined by the Cu and Ni contents of vessel materials, is considered a proper tool to assess the $RT_{PTS}$. The chemistry factors, which were obtained from the surveillance data of domestic reactor pressure vessels, were investigated and compared with those of Regulatory Guide 1.99 in this study. Regressions for ${\Delta}RT_{NDT}$ were performed to expect the chemistry factor as a function of Cu and Ni, and to estimate $RT_{PTS}$ margin. The margin analysis was performed by comparing the regression graphs and standard deviations with those of Regulatory Guide 1.99. The standard deviations calculated by using the domestic surveillance data for base metal and welds are almost same as the standard deviations which are suggested on Regulatory Guide 1.99, Rev.2.

Analysis of Reflux Cooling in the SG U-Tubes Under Loss of RHRS During Midloop Operation with Primary System Partly Open

  • Son, Young-Seok;Kim, Won-Seok;Kim, Kyung-Doo;Chung, Young-Jong;Chang, Won-Pyo
    • Nuclear Engineering and Technology
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    • v.30 no.2
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    • pp.112-127
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    • 1998
  • The present study is to assess the applicability of the best-estimate thermal-hydraulic codes, RELAP5/MOD3.2 and CATHARE2V1.3U, to the analysis of thermal-hydraulic behavior in PWRs during midloop operation following the loss of RHRS. The codes simulate an integral test, BETHSY 6.94, which was conducted in the large scale test facility of BETHSY in France. The test represents the accident where the loss of RHRS occurs during midloop operation with the pressurizer and upper head vents open and the sight level indicator broken. Besides, the hot legs are half filled with water and the upper parts of the primary cooling system are filled with nitrogen, with a letdown line open and only one SG available. The purposes of this study are to understand the physical phenomena associated with reflux cooling in the 5G U-tubes when noncondensable gas is present under low pressure and to assess the applicability of the codes to simulate the loss of RHRS event by comparing the predictions with the test results. The results of the study may contribute to actual applications for plant safety evaluation and description of the emergency operating procedure.

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Flood Risk for Power Plant using the Hydraulic Model and Adaptation Strategy

  • Nguyen, Thanh Tuu;Kim, Seungdo;Van, Pham Dang Tri;Lim, Jeejae;Yoo, Beomsik;Kim, Hyeonkyeong
    • Journal of Climate Change Research
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    • v.8 no.4
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    • pp.287-295
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    • 2017
  • This paper provides a mathematical approach for estimating flood risks due to the effects of climate change by developing a one dimensional (1D) hydraulic model for the mountainous river reaches located close to the Yeongwol thermal power plant. Input data for the model, including topographical data and river discharges measured every 10 minutes from July $1^{st}$ to September $30^{th}$, 2013, were imported to a 1D hydraulic model. Climate change scenarios were estimated by referencing the climate change adaptation strategies of the government and historical information about the extreme flood event in 2006. The down stream boundary was determined as the friction slope, which is 0.001. The roughness coefficient of the main channels was determined to be 0.036. The results show the effectiveness of the riverbed widening strategy through the six flooding scenarios to reduce flood depth and flow velocity that impact on the power plant. In addition, the impact of upper Namhan River flow is more significant than Dong River.