• Title/Summary/Keyword: critical energy

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Improvement of Liquid Droplet Entrainment Model in the COBRA-TF Code

  • Ha, Kwi-Seok;Jeong, Jae-Jun;Sim, Suk-Ku
    • Nuclear Engineering and Technology
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    • v.30 no.3
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    • pp.181-193
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    • 1998
  • The COBRA-TF liquid droplet entrainment models have been assessed and improved through various experiments. The COBRA-TF code uses the Wurtz entrainment model in the film mist flow regime and the mechanistic model based on the critical Weber number and critical vapor velocity in the hot wall flow regimes, respectively. The Wurtz model has been replaced with the modified Sugawara model. The assessment against the experiments by Hewitt, Keeys, Yanai, and Whalley showed the modified Sugawara model better predicts the steam-water as well as the air-water experiments for the film mist flow regime. For hot wall flow regime, the COBRA-TF entrainment model was modified using two methods, one with an increased critical Weber number and the other with the Yonomoto's critical vapor velocity model. The modified models were assessed using the FLECHT-SEASET bottom reflood tests. The results showed that the Yonomoto model best predicts the quenching time, whereas the local maximum rod temperature was not affected much.

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타원편광분석기를 이용한 Cd1-xMgxTe (0$\leq$x$\leq$0.5) alloy film의 유전율함수 연구

  • 구민상;이민수;김태중;김영동;박인규
    • Proceedings of the Korean Vacuum Society Conference
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    • 2000.02a
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    • pp.83-83
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    • 2000
  • MBE법으로 성장시킨 Cd1-xMgxTe 박막을 조성비 (x=0, 0.23, 0.32, 0.43)에 따라 타원편광 분석기로 측정하여 연구하였다. E0 critical point energy 아래에서 나타나는 간섭무늬를 제거하기 위해 multilayer calculation을 수행했고 ellipsometric data를 2번 미분하여 계산하는 Critical Point Parabolic Band(CPPB) model을 사용하여 E0, E0+Δ0, E1, E1,+Δ1, and E0'critical point energy 들을 구할 수 있었다. 특히 E2 peak region 에서는 종전의 고상시료 (bulk)에서 측정 발표된 값보다도 매우 높고 명확한 <$\varepsilon$2>값이 측정되어, E2와 E、0 peak가 명확하게 분리되는 것을 볼 수 있었다. 또한 Mg의 조성비에 따라 critical point energy 가 linear 하게 변화됨이 관측되었다.

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Experimental study on the influence of heating surface inclination angle on heat transfer and CHF performance for pool boiling

  • Wang, Chenglong;Li, Panxiao;Zhang, Dalin;Tian, Wenxi;Qiu, Suizheng;Su, G.H.;Deng, Jian
    • Nuclear Engineering and Technology
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    • v.54 no.1
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    • pp.61-71
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    • 2022
  • Pool boiling heat transfer is widely applied in nuclear engineering fields. The influence of heating surface orientation on the pool boiling heat transfer has received extensive attention. In this study, the heating surface with different roughness was adopted to conduct pool boiling experiments at different inclination angles. Based on the boiling curves and bubble images, the effects of inclination angle on the pool boiling heat transfer and critical heat flux were analyzed. When the inclination angle was bigger than 90°, the bubble size increased with the increase of inclination angle. Both the bubble departure frequency and critical heat flux decreased as the inclination angle increased. The existing theoretical models about pool boiling heat transfer and critical heat flux were compared. From the perspective of bubble agitation model and Hot/Dry spot model, the experimental phenomena could be explained reasonably. The enlargement of bubble not only could enhance the agitation of nearby liquid but also would cause the bubble to stay longer on the heating surface. Consequently, the effect of inclination angle on the pool boiling heat transfer was not conspicuous. With the increase of inclination angle, the rewetting of heating surface became much more difficult. It has negative effect on the critical heat flux. This work provides experimental data basis for heat transfer and CHF performance of pool boiling.

A study on the Dynamic Fracture Toughness for Polymeric Materials (폴리머재료의 파괴인성치에 관한 연구)

  • 최영식;박명균
    • Proceedings of the Safety Management and Science Conference
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    • 2001.05a
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    • pp.311-317
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    • 2001
  • The notched Charpy and Izod impact tests are the most prevalent techniques used to characterize the effects of high impulse loads on ploymeric materials. An analysis method for rubber toughened PVC is suggested to evaluate critical strain energy release rates(Gc) from the Charpy impact energy measurements. An Instrumented Charpy Impact tester was used to extract ancillary information concerning fracture properties in addition to total fracture properties and maximum critical loads. The stress intensity factor Kd was computed for varying amounts of rubber contents from the obtained maximum critical loads and also toughening effects were investigated as well.

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A Study on the Autoignition of Granulated Activated Carbon with Change of Oxygen Concentration (산소농도 변화에 따른 입상활성탄의 자연발화에 관한 연구)

  • 목연수;최재욱;류동현;최일곤;김상렬
    • Journal of the Korean Society of Safety
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    • v.10 no.2
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    • pp.84-91
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    • 1995
  • The characteristics of critical spontaneous ignition of granulated activated carbon were investigated In atmospheres of differing oxygen concentration. At the same concentration the larger vessels yielded the lower critical spontaneous ignition temperature. At the same vessel, as the concentration of oxygen was reduced, Ignition occurred later and at higher ambient temperature, and critical spontaneous ignition temperature increased. The apparent activation energy calculated from the Frank-Kamenetskii's ignition theory appeared to be the slight different value respectively and the mean apparent activation energy was 19850㎈/㏖.

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A study on the Determination of Fractuye Parameters for Rubber Toughened Polymeric Materials Using Instrumented Charpy Impact Test (샤피충격시험기를 이용한 고무보강 폴리머재료의 파괴인자 결정에 관한연구)

  • Choi, Young-Sic;Park, Myung-Kyun;Bahk, S.M.
    • Proceedings of the KSME Conference
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    • 2001.06a
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    • pp.389-394
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    • 2001
  • The notched Charpy and Izod impact tests arc the most prevalent techniques used to characterize the effects of high impulse loads on ploymeric materials. An analysis method for rubber toughened PVC is suggested to evaluate critical strain energy release rates(Gc) from the Charpy impact energy measurements. An Instrumented Charpy impact tester was used to extract ancillary information concerning fracture properties in addition to total fracture properties and maximum critical loads. The stress intensity factor Kd was computed for varying amounts of rubber contents from the obtained maximum critical loads and also toughening effects were investigated as well.

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A Study on Fracture Parameters for PVC/MBS Composites under Low Velocity Impact (저속 충격시 PVC/MBS재료의 파괴특성에 관한 연구)

  • 최영식;박명균;박세만
    • Proceedings of the Korean Society of Precision Engineering Conference
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    • 2002.10a
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    • pp.837-840
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    • 2002
  • An analysis method for rubber toughened PVC is suggested to evaluate critical dynamic strain energy release rates($G_c$) from the Charpy impact energy measurements. An instrumented Charpy impact tester was used to extract ancillary information concerning fracture parameters in addition to total fracture energies and maximum critical loads. The dynamic stress intensity factor $K_{Id}$ was computed for varying amounts of rubber contents from the obtained maximum critical loads and also toughening effects were investigated as well. The fracture surfaces produced under low velocity impact fur PVC/MBS composites were investigated by SEM. The results show that MBS rubber is very effective reinforcement material for toughening PVC.C.

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An Experimental Study on Heat Transfer Characteristics Just Before Critical Heat Flux in Uniformly Heated Vertical Annulus Under a Wide Range of Pressures

  • Chun, Se-Young;Moon, Sang-Ki;Chung, Heung-June;Chung, Moon-Ki
    • Nuclear Engineering and Technology
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    • v.34 no.4
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    • pp.269-285
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    • 2002
  • Water heat transfer experiments were carried out in a uniformly heated annulus with a wide range of pressure conditions. The local heat transfer coefficients for saturated water (low boiling have been measured just before the occurrence of the critical heat flux (CHF) along the length of the heated section. The trends of the measured heat transfer coefficients were quite different from the conventional understanding for the heat transfer of saturated flow boiling. This discrepancy was explained from the nucleate boiling in the liquid film of annular flow under high heat flux conditions. The well-known correlations were compared with the measured heat transfer coefficients. The Shah and Kandlikar correlations gave better prediction than the Chen correlation. However, the modified Chen correlation proposed in the present work showed the best agreement with the present data among correlations examined .

AN OVERVIEW OF RISK QUANTIFICATION ISSUES FOR DIGITALIZED NUCLEAR POWER PLANTS USING A STATIC FAULT TREE

  • Kang, Hyun-Gook;Kim, Man-Cheol;Lee, Seung-Jun;Lee, Ho-Jung;Eom, Heung-Seop;Choi, Jong-Gyun;Jang, Seung-Cheol
    • Nuclear Engineering and Technology
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    • v.41 no.6
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    • pp.849-858
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    • 2009
  • Risk caused by safety-critical instrumentation and control (I&C) systems considerably affects overall plant risk. As digitalization of safety-critical systems in nuclear power plants progresses, a risk model of a digitalized safety system is required and must be included in a plant safety model in order to assess this risk effect on the plant. Unique features of a digital system cause some challenges in risk modeling. This article aims at providing an overview of the issues related to the development of a static fault-tree-based risk model. We categorize the complicated issues of digital system probabilistic risk assessment (PRA) into four groups based on their characteristics: hardware module issues, software issues, system issues, and safety function issues. Quantification of the effect of these issues dominates the quality of a developed risk model. Recent research activities for addressing various issues, such as the modeling framework of a software-based system, the software failure probability and the fault coverage of a self monitoring mechanism, are discussed. Although these issues are interrelated and affect each other, the categorized and systematic approach suggested here will provide a proper insight for analyzing risk from a digital system.