• Title/Summary/Keyword: Out-pile Performance Test

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Preliminary Study for the Reliability Assurance on Results and Procedure of the Out-pile Mechanical Characterization Test for a Fuel Assembly; Lateral Vibration Test(I) (핵연료 집합체 노외성능시험의 절차와 결과에 대한 신뢰성확보를 위한 예비고찰; 횡방향 진동특성시험(I))

  • Lee, Kang-Hee;Yoon, Kyung-Ho;Kim, Hyung-Kyu
    • Proceedings of the KSME Conference
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    • 2007.05a
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    • pp.1854-1858
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    • 2007
  • The reliability assurance with respect to the test procedure and results of the out-pile mechanical performance test for the nuclear fuel assembly is an essential task to assure the test quality and to get a permission for fuel loading into the commercial reactor core. For the case of vibration test, which is carried out to obtain basic dynamic characteristics of the fuel assembly, proper management and appropriate calibration of instruments and devices used in the test, various efforts to minimize the possible error during the test and signal acquisition process are needed. Additionally, the deep understanding both of the theoretical assumption and simplification cation for the signal processing/modal analysis and of the functions of the devices used in the test were highly required. Finally, to verify the test result to represent the accurate natural characteristics of the structure, the proper correlation analysis between the theoretical and experimental method has to be carried out. In this study, the overall procedure and result of lateral vibration test for the fuel assembly's mechanical characterization were briefly introduced. A series of measures to assure and improve the reliability of the vibration test were discussed.

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Structural Performance Evaluation of Bolt Connection for Half-sphere Joint between PHC Pile and Steel Column (강재기둥-PHC 파일 간 반구형 접합부(HAT Joint)의 볼트 연결에 대한 구조성능평가)

  • Oh, Jintak;Kim, Sang-Bong;Kim, Young-Sik;Ju, Young K.
    • Journal of Korean Association for Spatial Structures
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    • v.15 no.4
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    • pp.65-72
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    • 2015
  • To overcome the weakness of spread foundation in large space structure, the research of precast pile for replace spread foundation have been conducted. The new type of joint between PHC pile and steel column is named HAT Joint(Hollow hAlf-sphere cast-sTeel Joint). It connected PHC Pile by bolt that verification of bolt connection should be accomplished. In this paper, pull-out test and flexural performance for HAT Joint to verifying the bolt connection is explained. As a result, the pull-out and flexural capacities of bolt were checked to use in real structure. Furthermore, the equation of pull-out strength was proposed.

IRRADIATION TEST OF MOX FUEL IN THE HALDEN REACTOR AND THE ANALYSIS OF MEASURED DATA WITH THE FUEL PERFORMANCE CODE COSMOS

  • WIESENACK WOLFGANG;LEE BYUNG-HO;SOHN DONG-SEONG
    • Nuclear Engineering and Technology
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    • v.37 no.4
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    • pp.317-326
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    • 2005
  • The burning-out of excess plutonium from the reprocessing of spent nuclear fuel and from the dismantlement of nuclear weapons is recently emphasized due to the difficulties in securing the final repository for the spent fuel and the necessity to consume the ex-weapons plutonium. An irradiation test in the Halden reactor was launched by the OECD Halden Reactor Project (HRP) to investigate the in-pile behavior of plutonium-embedded fuel as a form of mixed oxide (MOX) and of inert matrix fuel (IMF). The first cycle of irradiation was successfully accomplished with good integrity of test fuel rods and without any undesirable fault of instrumentations. The test results revealed that the MOX fuel is more stable under irradiation environments than IMF. In addition, MOX fuel shows lower thermal resistance due to its better thermal conductivity than IMF. The on-line measured in-pile performance data of attrition milled MOX fuel are used in the analysis of the in-pile performance of the fuel with the fuel performance code, COSMOS. The COSMOS code has been developed for the analysis of MOX fuel as well as $UO_2$ fuel up to high burnup and showed good capability to analyze the in-reactor behavior of MOX fuel even with different instrumentation.

Pressure Drop and Flow-Induced Vibration Test for the HANARO Non-instrumented Irradiation Test Rig of Annular Fuel Pellet (환형소결체 하나로 조사시험용 무계장 리그의 차압 및 유동유발 진동시험)

  • Lee, Kang-Hee;Kim, Dae-Ho;Bang, Jae-Gun
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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    • 2007.11a
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    • pp.281-286
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    • 2007
  • Needs of fuel's performance evaluation for the dual-cooled fuel pellet (annular shape) necessitate the irradiation test in the test reactor. Irradiation test rig for the HARARO reactor, which is a special-purposed equipment used for material, irradiation and creep test, must satisfy the operational requirement on the hydraulic characteristics and structural integrity. In this paper, pressure drop and flow-induced vibration test for the newly developed non-instrumented test rig were carried out using FIVPET as a out-pile evaluation test. The test results show that the new test rig satisfy the HANARO operational requirement with sufficient margin. The spectral response characteristics of the flow-induced vibration of the test rid were also discussed.

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Performance-based comparison of energy pile of various heat exchange pipe arrangement by in-situ thermal response test (현장 열응답 시험을 통한 에너지파일의 열교환파이프 배열 방식에 따른 성능 비교)

  • Min, Sunhong;Koh, Hyungseon;Yoo, Jaihyun;Jung, Kyoungsik;Lee, Youngjin;Choi, Hangseok
    • 한국신재생에너지학회:학술대회논문집
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    • 2011.05a
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    • pp.196.1-196.1
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    • 2011
  • In this study, a test bed was constructed in order to evaluate thermal efficiency of the energy pile which carries out combined roles of a structural foundation and of a heat exchanger. The energy pile in this study is designed as a large-diameter drilled shaft equipped with the heat exchange pipes which configures a W-shape and an S-shape. The drilled shaft reached to the depth of 60 m whilst the heat exchange pipes were installed to about 30 m deep from the ground surface. The W-shaped and S-shaped heat exchange pipes were installed in the opposite sections of the same drilled shaft. In-situ thermal response tests were performed for both the shapes of heat exchange pipes. To avoid underestimating the thermal performance due to hydration heat of concrete inside the drilled shaft, the in-situ thermal response tests for the energy pile were performed after four weeks since the installation of the energy pile.

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Measurement of Pile Load Transfer using Optical Fiber Sensors (광섬유 센서에 의한 말뚝 하중전이 측정)

  • 오정호;이원제;이우진
    • Proceedings of the Korean Geotechical Society Conference
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    • 1999.10a
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    • pp.397-404
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    • 1999
  • It is essential to measure load transfer mechanism of pile to check the appropriateness of assumptions made for design purpose and to continuously monitor the behavior of pile foundation. Through many attempts to monitor the behavior of super-structure in civil engineering area using several optical fiber sensors have been made, application of optical fiber sensor technology on pile foundation has not been tried up to now. Load transfer of model piles during compression loading was measured by optical fiber sensors and compared with the measurement by strain gauges. Fiber Bragg Grating(FBG) sensor system was used since it has many advantages, such as easy multiplexing, high sensitivity, and simple fabrication. Besides the model pile tests, uniaxial tension test of steel bar and compression tests of mortar specimen were carried out to evaluate the performance of FBG sensors in embedded environments. The shift of refilming wavelength due to the strain in FBG sensor is converted to the strain at sensor location and the dependence between them is 1.28 pm/${\mu}$ strain. FBG sensors embedded in model pile showed a better survivability than strain gauges. Measured results of load transfer by both FBG sensors and strain gauges were similar, but FBG sensors showed a smoother trend than those by strain gauge. Based on the results of model pile test, it was concluded that the use of FBG sensor for strain measurement in pile has a great potential for the analysis of pile load transfer.

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Evaluation of Field Applicability of Helical Pile Using Hexagon Joints (육각형 이음부를 이용한 회전관입말뚝의 현장적용성 평가)

  • Jeong, Sangguk
    • The Journal of Engineering Geology
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    • v.30 no.4
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    • pp.635-648
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    • 2020
  • Performance improvement of helical piles in static load tests using hexagon joints that do not require welding or bolting was investigated. Two sites were selected for pile field tests to evaluate their bearing capacity. Static and pull-out load tests were undertaken to assess the method for estimating bearing capacity. The field tests indicated that the bearing capacity of the gravity grout pile was ≥600 kN in the static load test, consistent with the AC 358 Code. The non-grout pile had a bearing capacity of ≤600 kN, suggesting that gravity grouting is required. Field pile load-test results were used to establish the bearing capacity equation, based on a small number of helical pile.

The Construction Work Completion of the Fuel Test Loop (핵연료 노내조사시험설비 설치공사 완료)

  • Park, Kook-Nam;Lee, Chung-Young;Chi, Dae-Young;Park, Su-Ki;Shim, Bong-Sik;Ahn, Sung-Ho;Kim, Hark-Rho;Lee, Jong-Min
    • Proceedings of the KSME Conference
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    • 2007.05a
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    • pp.291-295
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    • 2007
  • FTL(Fuel Test Loop) is a facility that confirms performance of nuclear fuel at a similar irradiation condition with that of nuclear power plant. FTL consists of In-Pile Test Section (IPS) and Out-Pile System (OPS). FTL construction work began on August, 2006 and ended on March, 2007. During Construction, ensuring the worker's safety was the top priority and installation of the FTL without hampering the integrity of the HANARO was the next one. Task Force Team was organized to do a construction systematically and the communication between members of the task force team was done through the CoP(community of Practice) notice board provided by the Institute. The installation works were done successfully overcoming the difficulties such as on the limited space, on the radiation hazard inside the reactor pool, and finally on the shortening of the shut down period of the HANARO. Without a sweet of the workers of the participating company of HEC(Hyundae Engineering Co, Ltd), HDEC(HyunDai Engineering & Construction Co. Ltd), equipment manufacturer, and the task force team, it is not possible to install the FTL facility within the planned shutdown period. The Commissioning of the FTL is on due to check the function and the performance of the equipment and the overall system as well. The FTL shall start operation with high burn up test fuels in early 2008 if the commissioning and licensing progress on schedule.

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A Numerical Analysis of Soil-Pile Systems for Pile Load Tests at a Korean Site (국내 말뚝재하시험에 대한 지반-말뚝계의 수치해석)

  • Oh, Se-Boong;Ahn, Tae-Kyong;Choi, Yong-Kyu
    • Journal of Ocean Engineering and Technology
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    • v.13 no.1 s.31
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    • pp.94-104
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    • 1999
  • In order to evaluate the performance of axially of laterally loaded piles experimentaly, pile load tests can be carried out at the site Otherwise stress analyses or subgrade reaction analyses can solve the problem. In this study, stress analysis using FLAC code and subgrade reaction analyses using load transfer curves recommended by API(1993) were performed consistently on the basis of a result of site investigations, and the result of analyses was compared with the measured. As a result the behavior of pile heads was analyzed accurately for both axially and laterally loaded tests. Furthermore axially transferred loads were calculated appropriately for the measured and axial loads were transferred mainly mainly by the frictional resistance rather than by the tip resistance. Consequently, it can be commented that both analysis methods of soil-pile systems are applicable at teh objective site and that solutions may be more accurate if material properties from the site investigation are more explicit.

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The Assembly and Test of Pressure Vessel for Irradiation (조사시험용 압력용기의 조립 및 시험)

  • Park, Kook-Nam;Lee, Jong-Min;Youn, Young-Jung;June, Hyung-Kil;Ahn, Sung-Ho;Lee, Kee-Hong;Kim, Young-Ki;Kennedy, Timothy C.
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.33 no.2
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    • pp.179-184
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    • 2009
  • The Fuel Test Loop(FTL) which is capable of an irradiation testing under a similar operating condition to those of PWR(Pressurized Water Reactor) and CANDU(CANadian Deuterium Uranium reactor) nuclear power plants has been developed and installed in HANARO, KAERI(Korea Atomic Energy Research Institute). It consists of In-Pile Section(IPS) and Out-of Pile System(OPS). The IPS, which is located inside the pool is divided into 3-parts; the in-pool pipes, the IVA(IPS Vessel Assembly) and the support structures. The test fuel is loaded inside a double wall, inner pressure vessel and outer pressure vessel, to keep the functionality of the reactor coolant pressure boundary. The IVA is manufactured by local company and the functional test and verification were done through pressure drop, vibration, hydraulic and leakage tests. The brazing technique for the instrument lines has been checked for its functionality and performance. An IVA has been manufactured by local technique and have finally tested under high temperature and high pressure. The IVA and piping did not experience leakage, as we have checked the piping, flanges, assembly parts. We have obtained good data during the three cycle test which includes a pressure test, pressure and temperature cycling, and constant temperature.