• 제목/요약/키워드: Steady State cycle

검색결과 185건 처리시간 0.019초

Analysis and Implementation of High Step-Up DC/DC Convertor with Modified Super-Lift Technique

  • Fani, Rezvan;Farshidi, Ebrahim;Adib, Ehsan;Kosarian, Abdolnabi
    • Journal of Power Electronics
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    • 제19권3호
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    • pp.645-654
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    • 2019
  • In this paper, a new high step up DC/DC converter with a modified super-lift technique is presented. The coupled inductor technique is combined with the super-lift technique to provide a tenfold or more voltage gain with a proper duty cycle and a low turn ratio. Due to a high conversion ratio, the voltage stress on the semiconductor devices is reduced. As a result, low voltage ultra-fast recovery diodes and low on resistance MOSFET can be used, which improves the reverse recovery problems and conduction losses. This converter employs a passive clamp circuit to recycle the energy stored in the leakage inductance. The proposed convertor features a high conversion ratio with a low turn ratio, low voltage stress, low reverse recovery losses, omission of the inrush currents of the switch capacitor loops, high efficiency, small volume and reduced cost. This converter is suitable for renewable energy applications. The operational principle and a steady-state analysis of the proposed converter are presented in details. A 200W, 30V input, 380V output laboratory prototype circuit is implemented to confirm the theoretical analysis.

Flow Characteristics Analysis for the Chemical Decontamination of the Kori-1 Nuclear Power Plant

  • Cho, Seo-Yeon;Kim, ByongSup;Bang, Youngsuk;Kim, KeonYeop
    • 방사성폐기물학회지
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    • 제19권1호
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    • pp.51-58
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    • 2021
  • Chemical decontamination of primary systems in a nuclear power plant (NPP) prior to commencing the main decommissioning activities is required to reduce radiation exposure during its process. The entire process is repeated until the desired decontamination factor is obtained. To achieve improved decontamination factors over a shorter time with fewer cycles, the appropriate flow characteristics are required. In addition, to prepare an operating procedure that is adaptable to various conditions and situations, the transient analysis results would be required for operator action and system impact assessment. In this study, the flow characteristics in the steady-state and transient conditions for the chemical decontamination operations of the Kori-1 NPP were analyzed and compared via the MARS-KS code simulation. Loss of residual heat removal (RHR) and steam generator tube rupture (SGTR) simulations were conducted for the postulated abnormal events. Loss of RHR results showed the reactor coolant system (RCS) temperature increase, which can damage the reactor coolant pump (RCP)s by its cavitation. The SGTR results indicated a void formation in the RCS interior by the decrease in pressurizer (PZR) pressure, which can cause surface exposure and tripping of the RCPs unless proper actions are taken before the required pressure limit is achieved.

Effect of Steady-State Oxidation on Tensile Failure of Zircaloy Cladding

  • Kim, Taeho;Choi, Kyoung Joon;Yoo, Seung Chang;Lee, Yunju;Kim, Ji Hyun
    • 방사성폐기물학회지
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    • 제20권2호
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    • pp.161-170
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    • 2022
  • The effect of oxidation time on the characteristics and mechanical properties of spent nuclear fuel cladding was investigated using Raman spectroscopy, tube rupture test, and tensile test. As oxidation time increased, the Raman peak associated with the tetragonal zirconium oxide phase diminished and merged with the Raman peak associated with the monoclinic zirconium oxide phase near 333 cm-1. Additionally, the other tetragonal zirconium oxide phase peak at 380 cm-1 decreased after 100 d of oxidation, whereas the zirconium monoclinic oxide peak became the dominant peak. The oxidation time had no effect on the tube rupture pressure of the oxidized zirconium alloy tube. However, the yield and tensile stresses of the oxidized nuclear fuel cladding tube decreased after 100 d of oxidation. The results of the scanning electron microscopy and transmission electron microscopy were represented with the in-situ Raman analysis result for the oxide characteristics generated on the cladding of spent nuclear fuel.

Development of nodal diffusion code RAST-V for Vodo-Vodyanoi Energetichesky reactor analysis

  • Jang, Jaerim;Dzianisau, Siarhei;Lee, Deokjung
    • Nuclear Engineering and Technology
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    • 제54권9호
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    • pp.3494-3515
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    • 2022
  • This paper presents the development of a nodal diffusion code, RAST-V, and its verification and validation for VVER (vodo-vodyanoi energetichesky reactor) analysis. A VVER analytic solver has been implemented in an in-house nodal diffusion code, RAST-K. The new RAST-K version, RAST-V, uses the triangle-based polynomial expansion nodal method. The RAST-K code provides stand-alone and two-step computation modes for steady-state and transient calculations. An in-house lattice code (STREAM) with updated features for VVER analysis is also utilized in the two-step method for cross-section generation. To assess the calculation capability of the formulated analysis module, various verification and validation studies have been performed with Rostov-II, and X2 multicycles, Novovoronezh-4, and the Atomic Energy Research benchmarks. In comparing the multicycle operation, rod worth, and integrated temperature coefficients, RAST-V is found to agree with measurements with high accuracy which RMS differences of each cycle are within ±47 ppm in multicycle operations, and ±81 pcm of the rod worth of the X2 reactor. Transient calculations were also performed considering two different rod ejection scenarios. The accuracy of RAST-V was observed to be comparable to that of conventional nodal diffusion codes (DYN3D, BIPR8, and PARCS).

Aerodynamic analysis of cambered blade H-Darrieus rotor in low wind velocity using CFD

  • Sengupta, Anal Ranjan;Biswas, Agnimitra;Gupta, Rajat
    • Wind and Structures
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    • 제33권6호
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    • pp.471-480
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    • 2021
  • This present paper leads to investigation of blade-fluid interactions of cambered blade H-Darrieus rotor having EN0005 airfoil blades using comprehensive Computational Fluid Dynamics (CFD) analysis to understand its performance in low wind streams. For several blade azimuthal angle positions, the effects of three different low wind speeds are studied regarding their influence on the blade-fluid interactions of the EN0005 blade rotor. In the prevailing studies by various researchers, such CFD analysis of H-Darrieus rotors are very less, hence it is needed to improve their steady-state performance in low wind velocities. Such a study is also important to obtain important performance insights of such thin cambered blade rotor in its complete rotational cycle. It has been seen that the vortex generated at the suction side of the EN0005 blade rolls back to its leading edge due to the camber of the blade and thus a peak velocity occurs near to the nose position of this blade at its leading edge, which leads to peak performance of this rotor. Again, in the returning phase of the blade, a secondary recirculating vortex is generated that acts on the pressure side of EN0005 blade rotor that increases the performance of this cambered EN0005 blade rotor in its downstream position as well. Here, the aerodynamic performances have been compared considering Standard k-ε and SST k-ω models to check the better suited turbulence model for the cambered EN0005 blade H-Darrieus rotor in low tip speed ratios.

Modelling of the fire impact on CONSTOR RBMK-1500 cask thermal behavior in the open interim storage site

  • Robertas Poskas;Kestutis Rackaitis;Povilas Poskas;Hussam Jouhara
    • Nuclear Engineering and Technology
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    • 제55권7호
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    • pp.2604-2612
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    • 2023
  • Spent nuclear fuel and long-lived radioactive waste must be carefully handled before disposing them off to a geological repository. After the pre-storage period in water pools, spent nuclear fuel is stored in casks, which are widely used for interim storage. Interim storage in casks is very important part in the whole cycle of nuclear energy generation. This paper presents the results of the numerical study that was performed to evaluate the thermal behavior of a metal-concrete CONSTOR RBMK-1500 cask loaded with spent nuclear fuel and placed in an open type interim storage facility which is under fire conditions (steady-state, fire, post-fire). The modelling was performed using the ANSYS Fluent code. Also, a local sensitivity analysis of thermal parameters on temperature variation was performed. The analysis demonstrated that the maximum increase in the fuel load temperatures is about 10 ℃ and 8 ℃ for 30 min 800 ℃ and 60 min 600 ℃ fires respectively. Therefore, during the fire and the post-fire periods, the fuel load temperatures did not exceed the 300 ℃ limiting temperature set for an RBMK SNF cladding for long-term storage. This ensures that fire accident does not cause overheating of fuel rods in a cask.

터보펌프 공급식 액체 로켓엔진의 시동 과도 해석

  • 박순영;남창호;문인상;설우석
    • 항공우주기술
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    • 제4권2호
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    • pp.142-152
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    • 2005
  • 액체로켓 엔진시스템 개발에 있어서 시동부터 정상상태까지의 시동특성은 안정된 시동의 재현성을 확보하여 신뢰도를 높이는 것과 과도상태의 시간을 단축하는 두 가지 목표를 만족하는 방향으로 전개된다고 할 수 있다. 특히 우리나라와 같이 액체로켓 엔진 개발의 초기단계에서는 엔진시스템 시험의 경험이 없어, 시동에서 정상상태까지 과연 어느 정도의 시간이 필요할 것인가에 대한 예측이 힘들 수밖에 없다. 본 연구에서는 터보펌프 공급식 액체로켓 엔진의 각 구성품의 모델을 구성하여 시동 과도 해석을 수행할 수 있는 프로그램을 완성하였다. 이 프로그램을 이용하여 25톤급 가스발생기 사이클 엔진에 대한 시동 특성을 조사하여 시동에서 정상상태에 이르는 시간을 계산하였으며, 비정상 상태의 엔진시스템의 동특성을 밝힐 수 있었다.

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장방형 해분내의 세립 퇴적물 퇴적모형 (Modeling Sedimentation of Fine-grained Sediments in a Rectangular Basin)

  • Hyo Jin Kang
    • 한국해안해양공학회지
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    • 제3권1호
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    • pp.38-44
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    • 1991
  • 간단한 box 모형이 장방형 해분에서의 세립 퇴적물의 퇴적현상을 설명하기 위하여 이용되었으며. 이 모형에 필요한 침식 및 퇴적률의 계수를 조사하여 남해안 가막양만에 적용하여 보았다. 해분이 외해와 연결되어 있고 외해의 부유퇴적물 농도가 일정하면 해분내에서 한 조석 주기 동안의 평균 부유퇴적물 농도는 일정한 값을 유지하게 되고 조류의 게류시 부근에는 퇴적이 일어나고 최대 유속시 부근에는 바닥 퇴적물의 재부유 및 침식이 일어나는 것을 보여주고 있다. 가막양만 처럼 퇴적이 우세한 해분에서는 조석 주기 중 퇴적이 일어나는 시간과 최대 퇴적률이 침식에 비하여 크게 나타나고 있으며, 이러한 퇴적 우세 해분의 부유퇴적물 평균농도는 외해의 부유퇴적물 농도보다 낮은 값을 보이고 있다. 또한. 조류의 유속변화에 따른 해분내기 부유퇴적물 농도변화는 고조의 약 한 시간 전에 최대값을 나타내고 저조의 약 한 시간 후에 최소값을 나타낸다.

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황-요오드 수소 생산 공정의 분젠 반응 부분에서 부반응 제어 (The Control of Side Reactions in Bunsen Reaction Section of Sulfur-Iodine Hydrogen Production Process)

  • 이광진;홍동우;김영호;박주식;배기광
    • 한국수소및신에너지학회논문집
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    • 제19권6호
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    • pp.490-497
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    • 2008
  • For continuous operation of the sulfur-iodine(SI) thermochemical cycle, which is expected practical method for massive hydrogen production, suggesting operation conditions at steady state is very important. Especially, in the Bunsen reaction section, the Bunsen reaction as well as side reactions is occurring simultaneously. Therefore, we studied on the relation between the variation of compositions in product solution and side reactions. The experiments for Bunsen reaction were carried out in the temperature range, from 268 to 353 K, and in the $I_2/H_2O$ molar ratio of $0.094{\sim}0.297$ under a continuous flow of $SO_2$ gas. As the result, sulfur formed predominantly with increasing temperature and decreasing $I_2/H_2O$ molar ratios. The molar ratios of $H_2O/H_2SO_4$ and $HI/H_2SO_4$ in global system were decreased as the more side reaction occurred. A side reactions did not appear at $I_2/H_2O$ molar ratios, saturated with $I_2$, irrespective of the temperature change. We concluded that it caused by the increasing stability of an $I_{2x}H^+$ complex and a steric hindrance with increasing $I_2/HI$ molar ratios.

초임계 CO2 발전용 파워터빈을 지지하는 틸팅패드 베어링의 열윤활 해석 및 패드 온도 측정 (Thermal Analysis and Temperature Measurement of Tilting Pad Bearings Supporting a Power Turbine for the Supercritical CO2 Cycle Application)

  • 이동현;김병옥;임형수
    • Tribology and Lubricants
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    • 제34권2호
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    • pp.43-48
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    • 2018
  • This paper presents the thermohydrodynamic analysis of tilting journal pad bearings supporting a power turbine rotor applied to a 250 kW super-critical $CO_2$ cycle. In the analysis, the generalized Reynolds equation and 3D energy equation are solved to predict oil film temperature and the 3D heat conduction equation is solved for pad temperature. The power turbine rotor is supported by two tilting pad bearings consisting of five pads with an oil supply block between the pads. Copper backing pads with higher thermal conductivity compared to steel backing pads are adopted to improve thermal management. The predicted maximum pad temperature is around $55^{\circ}C$ which is approximately $15^{\circ}C$ higher than oil supply temperature. In addition, the predicted minimum film thickness is 50 mm at a rotating speed of 5,000 rpm. These results indicate that there is no issue in the thermal behavior of the bearing. An operation test is performed with a power turbine module consisting of a power turbine, a reduction gear and a generator. Thermocouples are installed at the 75% position from the leading edge of the pad to monitor pad temperature. The power turbine uses compressed air at a temperature of $250^{\circ}C$ in its operation. The steady state pad temperatures measured in the test show good agreement with the predicted temperatures.