• 제목/요약/키워드: energy loss

검색결과 3,491건 처리시간 0.061초

전동/발전기 코어에 의한 초전도 플라이휠 에너지 저장장치의 회전손실 특성 평가 (Rotational loss assessment of flywheel energy storage system by Motor/Generator core)

  • 이정필;한영희;정세용;한상철;정년호;성태현
    • 전기학회논문지
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    • 제56권10호
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    • pp.1775-1781
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    • 2007
  • In this paper, the rotational loss of the superconductor flywheel energy storage system (SFES) by motor/generator stator core was assessed. To do this, the vertical axial type SFES with journal type superconductor bearing was manufactured. To quantitatively assess the rotational loss by the stator core, the rotational losses by superconductor bearing and the degree of a vacuum were measured. In case of variation of the inner radius and outer radius of the stator core, the rotational losses were measured. From the experimental results, It is confirmed that the rotational loss can be reduced by means of the optimal stator core design.

구조물 연결부의 질량부과 효과 : SEA실험 및 해석 결과 비교 (Added Mass Effect on Structural Junction: Comparison of SEA Experimental Results with Analysis)

  • 김관주;김정태;윤태중;박봉현
    • 한국소음진동공학회:학술대회논문집
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    • 한국소음진동공학회 2002년도 춘계학술대회논문집
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    • pp.359-364
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    • 2002
  • Statistical energy method is widely used for the prediction of vibrational and acoustical behavior of complex structures, such as ship building and automobile in mid-, high frequency ranges. However. in order to convince this SEA result, it is important to verify estimated SEA parameters, e. g. modal density, energy in each subsystem, damping loss factor, coupling loss factor. with possible other method. For modal density parameter, the experimental estimations via Experimental Modal Analysis are checked with those from finite element method for both beam- plate and plate-plate cans. Loss factors are calculated by Lyon's simple method for the two subsystem. finally. modal experiments are carried out by varying the mass added on the junction of two subsystem for the purpose of investigating the influence on the coupling loss factor's behavior.

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심랭식공기분리공정에서 질소증류탑의 엑서지 해석 (Exergy Analysis of Nitrogen Distillation Column in the Cryogenic Air Separation Process)

  • 용평순;이성철
    • 한국초전도ㆍ저온공학회논문지
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    • 제4권1호
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    • pp.145-150
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    • 2002
  • The distillation column is one of large energy consumable units in the cryogenic air separation process and the accurate energy analysis of this unit is necessary for choice of energy saving process. In this work, the energy method was adopted for energy analysis of a cryogenic nitrogen distillation column. In order to designing the energy saving distillation column, the exergy distribution of feed air, exergy efficiency and exergy loss for process condition was investigated and the optimal process condition to minimize the exergy loss was found. The result from this work can be used as a guideline for the choice of the process design conditions and efficiency improvement of cryogenic distillation column.

Flow Distribution and Pressure Loss in Subchannels of a Wire-Wrapped 37-pin Rod Bundle for a Sodium-Cooled Fast Reactor

  • Chang, Seok-Kyu;Euh, Dong-Jin;Choi, Hae Seob;Kim, Hyungmo;Choi, Sun Rock;Lee, Hyeong-Yeon
    • Nuclear Engineering and Technology
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    • 제48권2호
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    • pp.376-385
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    • 2016
  • A hexagonally arrayed 37-pin wire-wrapped rod bundle has been chosen to provide the experimental data of the pressure loss and flow rate in subchannels for validating subchannel analysis codes for the sodium-cooled fast reactor core thermal/hydraulic design. The iso-kinetic sampling method has been adopted to measure the flow rate at subchannels, and newly designed sampling probes which preserve the flow area of subchannels have been devised. Experimental tests have been performed at 20-115% of the nominal flow rate and $60^{\circ}C$ (equivalent to Re ~ 37,100) at the inlet of the test rig. The pressure loss data in three measured subchannels were almost identical regardless of the subchannel locations. The flow rate at each type of subchannel was identified and the flow split factors were evaluated from the measured data. The predicted correlations and the computational fluid dynamics results agreed reasonably with the experimental data.

SEWGS 시스템을 위한 WGS 촉매들의 마모특성 (Attrition Characteristics of WGS Catalysts for SEWGS System)

  • 류호정;이동호;이승용;진경태
    • 한국수소및신에너지학회논문집
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    • 제25권2호
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    • pp.122-130
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    • 2014
  • Attrition characteristics of WGS catalysts for pre-combustion $ CO_2$ capture were investigated to check attrition loss of those catalysts, to check change of particle size distribution during attrition tests, and to determine solid circulation direction of WGS catalysts in a SEWGS system. The cumulative attrition losses of two catalysts increased with increasing time. However, attrition loss under humidified condition was lower than that under non-humidified condition case for long-term attrition tests. Between two catalysts, attrition loss of PC-29 catalyst was higher than that of commercial catalyst for long-term attrition tests. However, the commercial catalyst generated much more fines than PC-29 catalyst during attrition. Therefore, we conclude that the PC-29 catalyst is more suitable for fluidized bed operation if we take into account the separation efficiency of cyclone. Based on the results from the tests for the effect of humidity on the attrition loss, we selected solid circulation direction from SEWGS reactor to regeneration reactor because the SEWGS reactor contains more water vapor than regeneration reactor.

Integral effect tests for intermediate and small break loss-of-coolant accidents with passive emergency core cooling system

  • Byoung-Uhn Bae;Seok Cho;Jae Bong Lee;Yu-Sun Park;Jongrok Kim;Kyoung-Ho Kang
    • Nuclear Engineering and Technology
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    • 제55권7호
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    • pp.2438-2446
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    • 2023
  • To cool down a nuclear reactor core and prevent the fuel damage without a pump-driven active component during any anticipated accident, the passive emergency core cooling system (PECCS) was designed and adopted in an advanced light water reactor, i-POWER. In this study, for a validation of the cooling capability of PECCS, thermal-hydraulic integral effect tests were performed with the ATLAS facility by simulating intermediate and small break loss-of-coolant accidents (IBLOCA and SBLOCA). The test result showed that PECCS could effectively depressurize the reactor coolant system by supplying the safety injection water from the safety injection tanks (SITs). The result pointed out that the safety injection from IRWST should have been activated earlier to inhibit the excessive core heat-up. The sequence of the PECCS injection and the major thermal hydraulic transient during the SBLOCA transient was similar to the result of the IBLOCA test with the equivalent PECCS condition. The test data can be used to evaluate the capability of thermal hydraulic safety analysis codes in predicting IBLOCA and SBLOCA transients under an operation of passive safety system.

CFD ANALYSIS OF HEAVY LIQUID METAL FLOW IN THE CORE OF THE HELIOS LOOP

  • Batta, A.;Cho, Jae-Hyun;Class, A.G.;Hwang, Il-Soon
    • Nuclear Engineering and Technology
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    • 제42권6호
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    • pp.656-661
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    • 2010
  • Lead-alloys are very attractive nuclear coolants due to their thermo-hydraulic, chemical, and neutronic properties. By utilizing the HELIOS (Heavy Eutectic liquid metal Loop for Integral test of Operability and Safety of PEACER$^2$) facility, a thermal hydraulic benchmarking study has been conducted for the prediction of pressure loss in lead-alloy cooled advanced nuclear energy systems (LACANES). The loop has several complex components that cannot be readily characterized with available pressure loss correlations. Among these components is the core, composed of a vessel, a barrel, heaters separated by complex spacers, and the plenum. Due to the complex shape of the core, its pressure loss is comparable to that of the rest of the loop. Detailed CFD simulations employing different CFD codes are used to determine the pressure loss, and it is found that the spacers contribute to nearly 90 percent of the total pressure loss. In the system codes, spacers are usually accounted for; however, due to the lack of correlations for the exact spacer geometry, the accuracy of models relies strongly on assumptions used for modeling spacers. CFD can be used to determine an appropriate correlation. However, application of CFD also requires careful choice of turbulence models and numerical meshes, which are selected based on extensive experience with liquid metal flow simulations for the KALLA lab. In this paper consistent results of CFX and Star-CD are obtained and compared to measured data. Measured data of the pressure loss of the core are obtained with a differential pressure transducer located between the core inlet and outlet at a flow rate of 13.57kg/s.

원형 파일 방파제에 의한 반사율과 투과율 (Reflection and Transmission Coefficients by a Circular Pile Breakwater)

  • 조일형;고혁준
    • 한국해안해양공학회지
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    • 제19권1호
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    • pp.38-44
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    • 2007
  • Bennet 등(1992)이 제안한 수학적 모델을 사용하여 원형 파일 방파제에 의한 반사율과 투과율을 살펴보았다. 파가 파일 방파제를 통과하면서 갑작스런 단면형상의 변화로 박리현상이 발생하며 이로 인하여 파 에너지의 일부분이 소멸된다. 따라서 수학적 모델의 신뢰성을 높이기 위해서는 에너지 손실계수를 정확히 산정하는 것이 중요하다. 본 연구에서는 FLUENT 상용코드를 사용하여 2차원 난류유동을 해석하고 파일 방파제 전후의 압력차로부터 에너지 손실계수를 구하였다. 에너지 손실계수는 공극률의 함수이며, 둘 사이의 관계식을 제안하였다. 손실계수 산정식의 타당성을 검증하기 위하여 수리모형실험결과와 비교하였다. 4가지 공극률에 대하여 반사율과 투과율을 비교한 결과 해석결과와 모형실험결과는 잘 일치하고 있음을 확인하였다.