• Title/Summary/Keyword: thermal transient response

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Analysis of Integration Factor Effect in Dynamic-Structure-Fluid-Heat Coupled Time Transient Staggered Integration Scheme for Morton Effect Analysis (모튼이펙트 해석을 위한 동역학-구조-유체-열전달 시간과도응답 연성해석 시차적분법에서 시상수 효과 분석)

  • Suh, Junho;Jeung, Sung-Hwa
    • Tribology and Lubricants
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    • v.35 no.1
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    • pp.77-86
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    • 2019
  • The present study focuses on the effect of staggered integration factor (SIF) on Morton effect simulation results. The Morton effect is a synchronous rotordynamic instability problem caused by the temperature differential across the journal in fluid film bearings. Convection and conduction of heat in the thin film displaces the hot spot, which is the hottest circumferential position in the thin film, from -20 to 40 degrees ahead of the high spot, where the minimum film clearance is experienced. The temperature differential across the journal causes a bending moment and the corresponding thermal bow in the rotating frame acts like a distributed synchronous excitation in the fixed frame. This thermal bow may cause increased vibrations and continued growth of the synchronous orbit into a limit cycle. The SIF is developed assuming that the response of the rotor-lubricant-bearing dynamic system is much quicker than that of the bearing-journal thermal system, and it is defined as the ratio between the simulation time of the thermal system and the rotor-spinning period. The use of the SIF is unavoidable for efficient computing. The value of the SIF is chosen empirically by the software users as a value between 100 and 400. However, the effect of the SIF on Morton effect simulation results has not been investigated. This research produces simulation results with different values of SIF.

Effects of Zingiberis Rhizoma Pharmacopuncture Injected at GB30 and ST36 on Neuropathic Pain in Rats (환도(GB30) 및 족삼리(ST36) 건강약침이 신경병증성 통증 유발 흰쥐에 미치는 영향)

  • Hwang, Min Sub
    • Korean Journal of Acupuncture
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    • v.36 no.1
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    • pp.52-62
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    • 2019
  • Objectives : The objective of this study was to investigate the effects of Zingiberis Rhizoma Pharmacopuncture(ZP) at GB30 and ST36 in neuropathic pain induced SD rats by the block of Transient Receptor Potential Vanilloid 1(TRPV1). Methods : Neuropathic pain in rats was induced by tibial and common peroneal nerve transection of right leg. The rat subjects were divided into 6 groups : normal(Nor, n=5), control(Con, n=5), neuropathic pain plus 2 mg/kg ZP injection at GB30 and ST36(ZP-A, n=5), 10 mg/kg ZP(ZP-B, n=5), 20 mg/kg ZP(ZP-C, n=5) and 0.45 mg/kg Tramadol(Tra, n=5). Three days after the surgery, injections were administered once a day for 17 days. Withdrawal response of neuropathic rats' legs were measured by stimulating the paw of Right leg with von frey filament, acetone and radient heat on day 3, 7, 11, 15, 19 after surgery. After all treatments were completed, c-Fos in the midbrain central gray and TRPV1 & TRPA1 of DRG(L5) were analyzed. Results : Groups ZP-B and ZP-C showed a meaningful decrease in the withdrawal response of mechanical allodynia, thermal hyperalgesia and cold allodynia compared to the control group(p<0.05, p<0.01, p<0.001). Groups ZP-B and ZP-C showed a meaningful decrease in the expression of c-fos and TRPV1 protein level compared to the control group(p<0.05, p<0.01, p<0.001). Conclusions : These results suggest that Zingiberis Rhizoma Pharmacopuncture at GB30 and ST36 could decrease mechanical & cold allodynia and thermal hyperalgesia by block the TRPV1 on the model of neuropathic pain.

Temperature-Induced Stresses and Deformation in Composite Box Girder Bridges (합성 박스형 교량의 온도에 의한 응력 및 변형)

  • Chang, Sung Pil;Im, Chang Kyun
    • Journal of Korean Society of Steel Construction
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    • v.9 no.4 s.33
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    • pp.659-672
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    • 1997
  • Thermal response induced from nonlinear temperature distribution in composite box gilder bridges depends on several variables(environmental conditions, physical and material properties, location and orientation of bridge, and cross-section geometry). In this paper, parametric study are conducted in order to find the effects of variations of seasons, location and orientation of bridge, sectional geometry and some material properties on the axial deformation, curvature and stresses in composite box girder bridge. A two-dimensional transient finite element model to conduct this parametric studies is briefly presented. Firstly, the effects of the parameters on the diurnal variation of curvature are considered, and for the time of maximum curvature, on the distribution of temperature and stresses of composite box girder sectional are considered. Finally, some considerations about the influence of the parameters on the daily maximum values of axial deformation, curvature and stresses are carried out. The influence of thermal effect on structures is important as much as the influence of live or dead load in some cases. In the design of steel composite bridges, the thermal stresses calculated on the supposition that the temperature difference between the concrete slab and steel girder is $10^{\circ}C$ and the temperature distributions are uniform in concrete slab and steel girder can be underestimated.

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Using machine learning to forecast and assess the uncertainty in the response of a typical PWR undergoing a steam generator tube rupture accident

  • Tran Canh Hai Nguyen ;Aya Diab
    • Nuclear Engineering and Technology
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    • v.55 no.9
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    • pp.3423-3440
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    • 2023
  • In this work, a multivariate time-series machine learning meta-model is developed to predict the transient response of a typical nuclear power plant (NPP) undergoing a steam generator tube rupture (SGTR). The model employs Recurrent Neural Networks (RNNs), including the Long Short-Term Memory (LSTM), Gated Recurrent Unit (GRU), and a hybrid CNN-LSTM model. To address the uncertainty inherent in such predictions, a Bayesian Neural Network (BNN) was implemented. The models were trained using a database generated by the Best Estimate Plus Uncertainty (BEPU) methodology; coupling the thermal hydraulics code, RELAP5/SCDAP/MOD3.4 to the statistical tool, DAKOTA, to predict the variation in system response under various operational and phenomenological uncertainties. The RNN models successfully captures the underlying characteristics of the data with reasonable accuracy, and the BNN-LSTM approach offers an additional layer of insight into the level of uncertainty associated with the predictions. The results demonstrate that LSTM outperforms GRU, while the hybrid CNN-LSTM model is computationally the most efficient. This study aims to gain a better understanding of the capabilities and limitations of machine learning models in the context of nuclear safety. By expanding the application of ML models to more severe accident scenarios, where operators are under extreme stress and prone to errors, ML models can provide valuable support and act as expert systems to assist in decision-making while minimizing the chances of human error.

Experimental study on flame behavior within a porous ceramic burner (다공 세라믹 버너 내부의 화염 거동에 관한 실험)

  • Im, In-Gwon;Jeong, Seok-Ho
    • Transactions of the Korean Society of Mechanical Engineers B
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    • v.21 no.4
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    • pp.518-524
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    • 1997
  • Experimental studies on combustion phenomena within a porous ceramic burner are reported. Main interest of the present work is to investigate fundamental flame behaviors and their effects on the burner operation. Due to high thermal capacity of the porous ceramic materials, the response of flame to burning condition changes is slow and thus to have a stabilized flame is quite difficult and takes much time. It is found that the temperature profile obtained at downstream of the flame zone is not much sensitive to the movement of flame and the speed of flame movement is less than 0.1 mm/sec for the conditions tested. With the premixed LPG/air flame imbedded within the porous ceramic burner, stable combustion regions and unstable combustion regions leading to blowoff or flashback phenomena are observed and mapped on flow velocity versus equivalence ratio diagram. For the development of burner operation technique which is more practical and safe, intermittent burning technique, where the fuel or/and air is supplied to the burner intermittently, is proposed as one of the flame control methods for the porous ceramic burner and tested in this study. Through the experiment, it is realized that the proposed method is acceptable in respect to burner performance and give much flexibility in the operation of porous ceramic burner.

RESULTS OF THE TOTAL DOSE EXPERIMENT ON KITSAT-1 (우리별 1호에서의 총 방사선 측정 실험)

  • 이대희;신영훈;민경욱
    • Journal of Astronomy and Space Sciences
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    • v.14 no.1
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    • pp.80-86
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    • 1997
  • High energy particles in the earth's radiation belts cause transient and long term effects on electronic materials, devices, and integrated circuits on board the satellites. Hence, it is very important to have the information on the space radiation environment and the damage on the electronics caused by the se high energy particles. One of the radiation monitor devices frequently used in space is RADFET, a specially designed MOSFET with a thick gate oxide region. The present study focuses on the calibration of RADFET TOT500 using the $Co^{60}{\gamma}-ray$ source. The result shows that the response of RADFET is very sensitive to the change of temperature. The peculiar behavior observed in the TDE (Total Dose Experiment) on board the KITSAT-1 is identified as the thermal effect due to the change in the eclipse rate of the satellite.

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SAFETY OF THE SUPER LWR

  • Ishiwatari, Yuki;Oka, Yoshiaki;Koshizuka, Seiichi
    • Nuclear Engineering and Technology
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    • v.39 no.4
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    • pp.257-272
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    • 2007
  • Supercritical water-cooled reactors (SCWRs) are recognized as a Generation IV reactor concept. The Super LWR is a pressure-vessel type thermal spectrum SCWR with downward-flow water rods and is currently under study at the University of Tokyo. This paper reviews Super LWR safety. The fundamental requirement for the Super LWR, which has a once-through coolant cycle, is the core coolant flow rate rather than the coolant inventory. Key safety characteristics of the Super LWR inhere in the design features and have been identified through a series of safety analyses. Although loss-of-flow is the most important abnormality, fuel rod heat-up is mitigated by the "heat sink" and "water source" effects of the water rods. Response of the reactor power against pressurization events is mild due to a small change in the average coolant density and flow stagnation of the once-through coolant cycle. These mild responses against transients and also reactivity feedbacks provide good inherent safety against anticipated-transient-without-scram (ATWS) events without alternative actions. Initiation of an automatic depressurization system provides effective heat removal from the fuel rods. An "in-vessel accumulator" effect of the reactor vessel top dome enhances the fuel rod cooling. This effect enlarges the safety margin for large LOCA.

A Systems Engineering Approach to Ex-Vessel Cooling Strategy for APR1400 under Extended Station Blackout Conditions

  • Saja Rababah;Aya Diab
    • Journal of the Korean Society of Systems Engineering
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    • v.19 no.2
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    • pp.32-45
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    • 2023
  • Implementing Severe Accident Management (SAM) strategies is crucial for enhancing a nuclear power plant's resilience and safety against severe accidents conditions represented in the analysis of Station Blackout (SBO) event. Among these critical approaches, the In-Vessel Retention (IVR) through External Reactor Vessel Cooling (IVR-ERVC) strategy plays a key role in preventing vessel failure. This work is designed to evaluate the efficacy of the IVR strategy for a high-power density reactor APR1400. The APR1400's plant is represented and simulated under steady-state and transient conditions for a station blackout (SBO) accident scenario using the computer code, ASYST. The APR1400's thermal-hydraulic response is analyzed to assess its performance as it progresses toward a severe accident scenario during an extended SBO. The effectiveness of emergency operating procedures (EOPs) and severe accident management guidelines (SAMGs) are systematically examined to assess their ability to mitigate the accident. A group of associated key phenomena selected based on Phenomenon Identification and Ranking Tables (PIRT) and uncertain parameters are identified accordingly and then propagated within DAKOTA Uncertainty Quantification (UQ) framework until a statistically representative sample is obtained and hence determine the uncertainty bands of key system parameters. The Systems Engineering methodology is applied to direct the progression of work, ensuring systematic and efficient execution.

Design of Controller for Rapid Thermal Process Using Evolutionary Computation Algorithm and Fuzzy Logic (진화 연산 알고리즘과 퍼지 논리를 이용한 고속 열처리 공정기의 제어기 설계)

  • Hwang, Min-Woong;Do, Hyun-Min;Choi, Jin-Young
    • Journal of the Korean Institute of Intelligent Systems
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    • v.8 no.6
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    • pp.37-47
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    • 1998
  • This paper proposes a controller design method using the evolutionary computation algorithm and the fuzzy logic to control the wafer temperature in rapid thermal processing. First, we design the feedforward static controller to provide the control powers of the lamps for the given steady state temperature. Second, the feedforward dynamic controller is designed for the additional control powers to achieve a given transient response. These feedforward controllers are implemented by using the fuzzy logic to act as a global nonlinear controller over a wide range of operating points. The parameters of these controllers are optimized by using the evolutionary computation algorithm so that it can be used when the mathematical model is not available. In addition, the feedback error controller is introduced to compensate the feedforward controllers when there exist disturbances and modeling errors. The gain of feedback error controller is also obtained by the evolutionary computation algorithm. Through simulations, we verify the proposed control system can give a satisfactory performance.

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Analysis of Material Response Based on Chaboche Unified Viscoplastic Constitutive Equation; (CHABOCHE 통합 점소성 구성방정식을 이용한 재료거동해석)

  • Kwak, D.Y.;Im, Y.T.;Kim, J.B.;Lee, H.Y.;Yu, B.
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.20 no.11
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    • pp.3516-3524
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    • 1996
  • Service conditions for structures at elevated temperatures in nuclear power plant involve transient thermal and mechanical load levels that are severe enough to caeuse inelastic deformations due to creep and plasticity. Therefore, a systematic mehtod of inelastic analysis is needed for the design of structural components in nuclear poser plants subjected to such loading conditions. In the present investigation, the Chabodhe model, one of the unified viscoplastic constitutive equations, was selected for systematic inelastic analysis. The material response was integrated based on GMR ( generallized mid-point rule) time integral scheme and provided to ABAQUS as a material subroutine, UMAT program. By comparing results obtaned from uniaxial analysis using the developed UMAT program with those from Runge-Kutta solutions and experimentaiton, the validity of the adopted Chaboche model and the numerical stability and accuracy of the developed UMAT program were verified. In addition, the developed material subroutine was applied for uniaxial creep and tension analyses for the plate with a hole in the center. The application further demonstrates usefulness of the developed program.