• 제목/요약/키워드: Energy Release

검색결과 1,090건 처리시간 0.022초

정적연소기에서 점화장치가 열발생률과 잘량연소율에 미치는 영향에 관한 연구 (A Study on the Effects of Ignition Systems on the Heat Release Rate and Mass Fraction Burnt at a Constant Volume Combustion Chamber)

  • 송정훈;이기형;선우명호
    • 대한기계학회논문집B
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    • 제24권11호
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    • pp.1486-1496
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    • 2000
  • The initial flame kernel development and flame propagation in a constant volume combustion chamber is analyzed by the heat release rate and the mass fraction burnt. The combustion pressure is measured with a piezoelectric type pressure sensor. In order to evaluate the effects of ignition system and ignition energy on the flame propagation, four different ignition systems are designed and tested, and the ignition energy is varied by the dwell time. Several different spark plugs are also tested and examined to analysis the effects of electrodes on flame kernel development. The results show that the when the dwell time is increased, and when the spark plug gap is extended, heat release rate and the mass burnt fraction are increased. The materials and shapes of electrodes affect the flame development, because they change the energy transfer efficiency from electrical energy to chemical energy. The diameter of electrodes influences not only the heat release rate but also the mass burnt fraction as well.

An Experimental and Mathematical Study on the Effects of Ignition Energy and System on the Flame Kernel Development

  • Song, Jeonghoon;Sunwoo, Myoungho
    • Journal of Mechanical Science and Technology
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    • 제16권6호
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    • pp.829-838
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    • 2002
  • A constant volume combustion chamber is used to investigate the flame kernel development of gasoline air mixtures under various ignition systems, ignition energies and spark plugs. Three kinds of ignition systems are designed and assembled, and the ignition energy is controlled by the variation of the dwell time. Several kinds of spark plugs are also tested. The velocity of flame propagation is measured by a laser deflection method, and the combustion pressure is analyzed by the heat release rate and the mass fraction burnt. The results represent that as the ignition energy is increased by enlarging either dwell time or spark plug gap, the heat release rate and the mass fraction burnt are increased. The electrodes materials and shapes influence the flame kernel development by changing he transfer efficiency of electrical energy to chemical energy. The diameter of electrodes also influences the heat release rate and the burnt mass fraction.

균열을 내재한 회전체의 에너지방출률 (The Energy Release Rate for Cracks in a Rotating Continuum)

  • 이태원
    • 대한기계학회논문집
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    • 제19권2호
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    • pp.330-337
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    • 1995
  • For a rotating body with cracks, the new energy release rate equation is presented. The derived equation is different from the other researcher's results. It is a path-independent integral which excluded the derivatives of displacements near the crack tip, thereby improving the numerical accuracy of the energy release rate computation. Moreover, as the equation was derived on basis of the energy principle and non-linear elasticity without assumptions, it can applied to the cracked body with arbitrary shape under elastic-plastic deformation. Several examples are treated to demonstrate the efficiency and accuracy of the proposed method compared to existing methods.

연구로 2호기 중성자 조사 흑연의 Wigner 에너지 방출 특성 연구 (A Study on the Wigner Energy Release Characteristics of Irradiated Graphite of KRR-2)

  • 정경환;윤세훈;이동규;정종헌;이근우
    • 방사성폐기물학회지
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    • 제4권3호
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    • pp.209-216
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    • 2006
  • 중성자가 조사된 흑연에 내재되어 있는 Wigner 에너지를 배출시키는 방법의 하나인 가열냉각공정의 적용 예로 DSC(미분 주사선 열량계) 측정을 통해 흑연으로부터 Wigner 에너지가 배출되는 열 배출 특성을 연구하였다. 일정온도 상승 방법 에 의한 DSC 운전에서 중성자가 조사된 흑연을 가열냉각(annealing)하는 동안 배출되는 Wigner 에너지의 총량과 처리온도에 따른 배출속도를 측정하였다. 연구로 2호기(KRR-2) thermal column 내에 위치별로 중성자의 조사량에 차이가 나는 흑연 시료를 분말로 만들어 상온에서 $500^{\circ}C$까지의 온도 범위에서 DSC를 운전하고 이로부터 Wigner 에너지의 배출 속도를 측정하였다. 가열냉각 동안 중성자가 조사된 흑연에서 배출되는 Wigner 에너지의 배출 특성은 가변적 활성화 에너지 속도 식으로 잘 상관시킬 수 있었다.

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Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part I: SCIANTIX

  • Zullo, G.;Pizzocri, D.;Magni, A.;Van Uffelen, P.;Schubert, A.;Luzzi, L.
    • Nuclear Engineering and Technology
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    • 제54권8호
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    • pp.2771-2782
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    • 2022
  • When assessing the radiological consequences of postulated accident scenarios, it is of primary interest to determine the amount of radioactive fission gas accumulated in the fuel rod free volume. The state-of-the-art semi-empirical approach (ANS 5.4-2010) is reviewed and compared with a mechanistic approach to evaluate the release of radioactive fission gases. At the intra-granular level, the diffusion-decay equation is handled by a spectral diffusion algorithm. At the inter-granular level, a mechanistic description of the grain boundary is considered: bubble growth and coalescence are treated as interrelated phenomena, resulting in the grain-boundary venting as the onset for the release from the fuel pellets. The outcome is a kinetic description of the release of radioactive fission gases, of interest when assessing normal and off-normal conditions. We implement the model in SCIANTIX and reproduce the release of short-lived fission gases, during the CONTACT 1 experiments. The results show a satisfactory agreement with the measurement and with the state-of-the-art methodology, demonstrating the model soundness. A second work will follow, providing integral fuel rod analysis by coupling the code SCIANTIX with the thermo-mechanical code TRANSURANUS.

On-the-fly energy release per fission model in STREAM with explicit neutron and photon heating

  • Nhan Nguyen Trong Mai;Woonghee Lee;Kyeongwon Kim;Bamidele Ebiwonjumi;Wonkyeong Kim;Deokjung Lee
    • Nuclear Engineering and Technology
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    • 제55권3호
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    • pp.1071-1083
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    • 2023
  • The on-the-fly energy release per fission (OTFK) model is implemented in STREAM to continuously update the Kappa values during the depletion calculation. The explicit neutron and photon energy distribution, which has not been considered in previous STREAM versions, is incorporated into the existing on-the-fly model. The impacts of the modified OTFK model with explicit neutron and photon heating in STREAM on the power distribution, fuel temperature, and other core parameters during depletion with feedback calculations are studied using several problems from the VERA benchmark suit. Overall, the explicit heating calculation provides a better power map for the feedback calculations particularly when strong gamma emitters are present. Generally, the fuel temperature decreases when neutron and photon heating is employed because fission neutrons and gamma rays are transported away from their points of generation. This energy release model in STREAM indicates that gamma energy accounts for approximately 9.5%-10% of the total energy released, and approximately 2.4%-2.6% of the total energy released will be deposited in the coolant for the VERA 5, NuScale, and Yonggwang Unit 3 2D cores.

Estimation of Tritium Concentration in Groundwater around the Nuclear Power Plants Using a Dynamic Compartment Model

  • Choi, Heui-Joo;Lee, Han-Soo;Kang, Hee-Suk;Choi, Yong-Ho
    • Journal of Radiation Protection and Research
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    • 제28권3호
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    • pp.239-245
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    • 2003
  • Every nuclear power plant measured concentrations of tritium in groundwater and surface water around the plants periodically. It was not easy to predict the tritium concentration only with these measurement data in case of various release scenarios. KAERI developed a new approach to find the relationship between the tritium release rate and tritium concentration in the environment. The approach was based upon a dynamic compartment model. In this paper the dynamic compartment model was modified to predict the tritium behavior more accurately. The mechanisms considered for the transfer of tritium between the compartments were evaporation, groundwater flow, infiltration, runoff, and hydrodynamic dispersion. Time dependent source terms of the compartment model were introduced to refine the release scenarios. Also, transfer coefficients between the compartments were obtained using realistic geographical data. In order to illustrate the model various release scenarios were developed, and the change of tritium concentration in groundwater and surface water around the nuclear power plants was estimated.

유사등방성 이종재 접합계면 균열의 에너지 해방률에 관한 연구 (A Study on Energy Release Rate for Interface Cracks in Pseudo-isotropic Dissimilar Materials)

  • 이원욱;김진광;조상봉
    • 한국정밀공학회지
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    • 제20권7호
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    • pp.193-200
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    • 2003
  • The energy release rate for an interface crack in pseudo-isotropic dissimilar materials was obtained by the eigenfunction expansion method using the two-term William's type complex stress function. The complex stress function for pseudo-isotropic materials must be different from that for anisotropic materials. The energy release rate for an interface crack in pseudo-isotropic dissimilar materials was analyzed numerically by RWCIM. The results obtained were verified by comparing the other worker's results and discussed.

유사등방성 이종재 접합계면 균열의 에너지해방률에 대한 연구 (A Study on Energy Release Rate for Interface Cracks in Pseudo-isotropic Dissimilar Materials)

  • 이원욱;김진광;조상봉
    • 한국정밀공학회:학술대회논문집
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    • 한국정밀공학회 1997년도 추계학술대회 논문집
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    • pp.752-754
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    • 1997
  • The stress intensity factor for an interface crack in dissimilar materials has been obtained by many researchers. But research of the energy release rate for an interface crack in pseudo-isotropic dissimilar materials is insufficient yet. In this paper, the energy release rate for cracks in pseudo-isotropic dissimilar materials was obtained using eigenfunction expansion method and also analyzed numerically using the reciprocal work contour integral method. The results were verified by comparing with other worker's results.

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