• 제목/요약/키워드: Test Rod

검색결과 599건 처리시간 0.027초

매입형 FRP봉과 보강철물을 보강한 철근콘크리트 보의 구조성능 평가 (Evaluation of Structural Performance of Reinforced Concrete Beams Retrofitted by Embedded FRP Rod and Metal Fittings)

  • 하기주;신종학;하영주;강현욱
    • 콘크리트학회논문집
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    • 제24권4호
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    • pp.445-452
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    • 2012
  • 이 연구에서는 기존 철근콘크리트 건축물의 구조성능 향상을 위하여 매입형 FRP봉과 보강철물을 보강한 철근콘크리트 보의 구조성능을 평가하기 위하여 실험을 수행하였다. 매입형 FRP봉의 사용량, 보강철물 유무에 따라 총 7개의 실험체를 제작하고 실험을 수행하여 구조성능을 평가하였으며, 이 연구의 실험 결과를 근거로 다음과 같은 결론을 얻었다. 매입형 FRP봉 보강실험체(BCR 시리즈)의 경우 표준실험체(BSS)와 비교하여 21~55% 내력이 증가하였고, 매입형 FRP봉과 보강철물을 보강한 실험체(BCR-AC 시리즈)는 표준실험체(BSS)보다 최대내력이 21~63% 증가하였다. 그리고 매입형 FRP봉으로 보강된 실험체는 부착슬립, 피복분리 형태로 파괴되었으나, 매입형 FRP봉과 보강철물을 보강한 실험체는 보강철물의 구속효과로 부착슬립의 형태로 파괴되었다.

Drop Performance Test of Conceptually Designed Control Rod Assembly for Prototype Generation IV Sodium-Cooled Fast Reactor

  • Lee, Young-Kyu;Lee, Jae-Han;Kim, Hoe-Woong;Kim, Sung-Kyun;Kim, Jong-Bum
    • Nuclear Engineering and Technology
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    • 제49권4호
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    • pp.855-864
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    • 2017
  • The control rod assembly controls reactor power by adjusting its position during normal operation and shuts down chain reactions by its free drop under scram conditions. Therefore, the drop performance of the control rod assembly is important for the safety of a nuclear reactor. In this study, the drop performance of the conceptually designed control rod assembly for the prototype generation IV sodium-cooled fast reactor that is being developed at the Korea Atomic Energy Research Institute as a next-generation nuclear reactor was experimentally investigated. For the performance test, the test facility and test procedure were established first, and several free drop performance tests of the control rod assembly under different flow rate conditions were then carried out. Moreover, performance tests under several types and magnitudes of seismic loading conditions were also conducted to investigate the effects of seismic loading on the drop performance of the control rod assembly. The drop time of the conceptually designed control rod assembly for 0% of the tentatively designed flow rate was measured to be 1.527 seconds, and this agrees well with the analytically calculated drop time. It was also observed that the effect of seismic loading on the drop time was not significant.

표준관입시험시 롯드에 전달되는 해머의 낙하에너지 평가 1 (The Hammer Energy Delivered to the Drilling Rod in the SPT 1)

  • 조성민;정종홍;김동수;이우진
    • 한국지반공학회:학술대회논문집
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    • 한국지반공학회 2001년도 봄 학술발표회 논문집
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    • pp.469-476
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    • 2001
  • The Ν-value in the standard penetration test(SPT) is affected by the magnitude of the rod penetration energy transmitted from the falling hammer as well as the geotechnical characteristics of the ground. Understanding of the striking energy efficiency in the SPT equipment is getting important for that reason. The energy efficiencies of the doughnut hammer with the hydraulic lift system and the automatic trip hammer system were investigated through field tests using the instrumented rod and wave-signal acquisition systems including the pile driving analyzer(PDA) . The rod energy ratio, ΕR$\_$r/ was defined as the ratio of the energy delivered to the drilling rod to the potential free-fall energy of the hammer. It appears that the type of the hammer and lift/drop system had a strong influence on the energy transfer mechanism and ΕR$\_$r/ also varies according to the energy instrumentation system and the analysis methods.

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Water-Side Oxide Layer Thickness Measurement of the Irradiated PWR Fuel Rod by ECT Method

  • Park, Kwang-June;Chun, Yong-Bum
    • Nuclear Engineering and Technology
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    • 제29권2호
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    • pp.175-180
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    • 1997
  • It has been known that eater-side corrosion of fuel rods in nuclear reactor is accompanied with the metallic loss of wall thickness and hydrogen pickup in the fuel dadding tube. The fuel dad corrosion is one of the major factors to be controlled to maintain the fuel integrity during reactor operation. An oxide later thickness measuring device equipped with ECT probe system was developed by KAERI, and whose performance test was carried out in NDT(Non-destructive Test) hot-cell or PIE(Post Irradiation Examination) Facility. At first, the calibration/performance test was executed for the unirradiated standard specimen rod fabricated with several kinds of plastic thin films whose thickness ore predetermined, and the result of which showed a good precision within 10% of discrepancy. And then, hot test us peformed for the irradiated fuel rod selectively extracted from J44 fuel assembly discharged from Kori Unit-2. The data obtained with this device were compared with the metallographic result obtained from destructive examination in PIEF hot-cell on the same fuel rod to verify the validity of the measurement data.

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Mn-B 합금계 고강도 강의 동적 물성 (Dynamic Material Property of Mn-B Alloy High-Strength Steel)

  • 최창;홍성인
    • 한국정밀공학회지
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    • 제13권11호
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    • pp.124-131
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    • 1996
  • The dynamic material property of Mn-B ally high-strength steel is investigated through the rod impact test which is one of simple test methods for the analysis of the material behavior under high-strain-rate. Rod impact test is performed to produce the deformed shape of rod and analyzed by the one-dimensional theory based on conservation law and the two-dimensional hydrocode AUTODYN-2D. The dynamic yield stress is determined and compared with the static yield stress to investigate the strain-rate sensitivity of Mn-B alloy high-strength steel.

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Test Coil과 영구자석의 자기 특성 연구 (Study on Magnetic Property for Test Coil and Permanent Magnet)

  • 박윤범;김종욱;이재선
    • 한국자기학회지
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    • 제26권5호
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    • pp.154-158
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    • 2016
  • 원자력발전소의 원자로에는 노심 반응 속도를 제어하기 위하여 제어봉구동장치가 사용된다. 한국원자력연구원의 SMART 원자로는 원자로 가동 중 제어봉집합체의 위치를 확인하기 위하여 제어봉구동장치에 영구자석과 리드스위치로 구성되는 위치지시기가 설치된다. 원자로 가동 온도는 최대 $350^{\circ}C$로 고려되어 설계되며, 영구자석은 원자로 내에 설치된다. 반면에 리드스위치와 전기회로는 원자로 외부에 설치된다. Test coil은 리드스위치의 품질 검증을 위한 장비로서, 코일과 철심으로 구성되어 있다. 본 연구는 리드스위치에 미치는 Test coil과 영구자석의 자기 특성을 비교하고자 수행되었으며, 유한요소 전자기 시뮬레이션을 활용하였다.

슬리브관을 갖는 로드셀을 이용한 주퇴봉 당김력 계측시스템 개발 (A Development of the Recoil Rod Pull Force Measurement System Using the Load Cell with Sleeve)

  • 최주호;홍성수;유준
    • 제어로봇시스템학회논문지
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    • 제7권2호
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    • pp.152-159
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    • 2001
  • This paper presents a development of the recoil rod pull force measurement system suing the load cell with a sleeve normally available in the recoil system test. The commercial load cell cannot be used in the test of recoil system floating the breach contact point freely in the air. The load cell is designed and manufactured to meet the recoil system test condition. Theoretical analysis and experimental results show that the accuracy of the developed measurement system is within $\pm$0.5%. We notice that the measurement technique proposed in this paper is accurate and useful in the recoil rod pull force measurement of the recoil system.

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표준관입시험시 롯드에 전달되는 해머의 낙하에너지 평가 2 (The Hammer Energy Delivered to the Drilling Rod in the SPT 2)

  • 조성민;정종흥;이우진;김동수
    • 한국지반공학회:학술대회논문집
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    • 한국지반공학회 2002년도 봄 학술발표회 논문집
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    • pp.71-78
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    • 2002
  • The N-value from the standard penetration test(SPT) is affected by the magnitude of the rod penetration energy transmitted from the falling hammer as well as the geotechnical characteristics of the ground. Understanding of the striking energy efficiency in the SPT equipment is getting important for that reason. The energy efficiencies of the various type of equipment were investigated through field tests using the instrumented rod and wave-signal acquisition systems including the pile driving analyzer(PDA). The rod energy ratio, ERr was defined as the ratio of the energy delivered to the drilling rod to the potential free-fall energy of the hammer. It appears that the type of the hammer and lift/drop system had a strong influence on the energy transfer mechanism and ERr also varies according to the energy instrumentation system and the analysis methods.

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강봉댐퍼의 개수 및 Z 플레이트 사용에 따른 의존성 및 성능 평가 (Dependency and Performance Evaluation according to the Number of Steel Rod Dampers and the use of Z plates)

  • 이현호
    • 한국공간구조학회논문집
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    • 제23권4호
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    • pp.51-58
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    • 2023
  • In this study, the displacement dependence, strength, and energy dissipation capacity of the steel rod damper were evaluated. The test variables are the number of steel rod dampers and the lateral deformation prevention details. From test results, it was evaluated that the displacement dependence conditions in the structural design code were satisfied. The maximum strength and energy dissipation capacity increased linearly as the number of steel rod increased. In addition, the maximum strength and energy dissipation capacity were evaluated by more than 20 times increased by using of the lateral deformation prevention details.

실증용 탈피복 장치를 이용한 모의 핵연료 슬릿팅 시험 (Slitting Test of Simulated Fuel Rod by Using a Newly Developed Decladding Device)

  • 정재후;홍동희;김영환;박병석;이종광
    • 한국소성가공학회:학술대회논문집
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    • 한국소성가공학회 2006년도 춘계학술대회 논문집
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    • pp.141-144
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    • 2006
  • In this study, we developed a decladding device which separates 250 mm length of simulated nuclear spent fuel rod into the pallets and the pieces of the hulls after inserting the rod cut into the module with several pairs of blades. To improve the performance of the equipment, we considered some mechanisms to prevent the rod cut from being exposed or bounced into the hot-cell, to reduce the operation time, and to insert the rods automatically. It is expected that the newly developed system will contribute to prevent radioactive pollution in the hot-cell, reduce the operation time, and to increase the safety of the operators. As a result of the performance test for some mockup fuel rod cuts in the ACP(Advanced Spent Fuel Control Process) facility, it was verified that the decladding device could be applied to the actual fuel rod cut. And it will be able to use for a scale-up facility in the future.

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