• Title/Summary/Keyword: containment

Search Result 954, Processing Time 0.025 seconds

Influences of Water to Cement Ratio and Chemical Admixtures on the Quality of Inter-Locking Block (인터로킹 블록의 품질에 미치는 물시멘트비와 화학혼화제의 영향)

  • 이상태;김기철;신병철;김진선;한천구
    • Proceedings of the Korea Concrete Institute Conference
    • /
    • 1998.10c
    • /
    • pp.157-160
    • /
    • 1998
  • KS F 4419, which is dealt with the Inter-Locking block, states that water to cement ratio for manufacturing inter-locking block should be less than 25% and in KS F4419, the use of admixture is shown to be reluctant to recommend. In this paper, reinvestigation of some regulations in KS F 4419 are carried out. According to the experimental results, as W/C increases, flexural strength and compressive strength are tended to decrease, whereas they increases within certain range, Flexural strength and compressive strength have higher values in 1:2(W/C=35%), 1:4(W/C=45%) and 1:6(W/C=55%) of mix proportions. Moreover they have rather higher values with the containment of high range AE water-reducing agent. The absorption ratios decrease with the increase of W/C and the containment of high range AE water-reducing agent. Therefore, the regulations on the W/C and admixture in KS F 4419 reguire revision.

  • PDF

Cracking Behavior of RC Panel Subjected to Biaxial Tension (2축 인장을 받는 철근콘크리트 패널의 균열 거동)

  • 조재열;조남소;구은숙;김남식;전영선
    • Proceedings of the Korea Concrete Institute Conference
    • /
    • 2002.05a
    • /
    • pp.475-480
    • /
    • 2002
  • Tension tests of six half-thickness concrete containment wall elements were conducted as part of a Korea Atomic Energy Research Institute (KARRI) program. The aim of the KAERI test program is providing a test-verified analytical method for estimating capacities of concrete reactor containment buildings under internal overpressurization from postulated degraded core accidents. The data from the tests reported herein should be useful for benchmarking method that requires modeling of material behavior including concrete cracking and reinforcement/concrete interaction exhibited by the test. Major test variable is the compressive strength of concrete and its effect on the behavior of prestressed concrete panel subjected to biaxial tension.

  • PDF

The Study of Radiation Hardened Common Sensor Circuits using COTS Semiconductor Devices for the Nuclear Power Plant (상용 반도체 소자를 이용한 내방사선 원전 센서신호 공통회로 연구)

  • Kim, Jong-Yeol;Lee, Nam-Ho;Jung, Hyun-Kyu;Oh, Seung-Chan
    • The Transactions of The Korean Institute of Electrical Engineers
    • /
    • v.63 no.9
    • /
    • pp.1248-1252
    • /
    • 2014
  • In this study, we designed a signal processing module using a radiation hardened technology that can be applied to the all measurement sensors inside nuclear power plant containment. Also, for verification that it can be used for high-level radiation environment (Harsh environmental zone inside containment of NPP), we carried out evaluation tests for a designed module using a $Co^{60}$ gamma-ray source up to 12 kGy(Si). And, we had checked radiation hardening level that it has been satisfied up to 12 kGy(Si).

The Optimization for Type "C" LLRT Requirements of Containment Vessel (격납용기 Type "C" 누설률시험 요건 최적화)

  • Jung, Nam-Du;Kim, Jae-Dong;Kim, In Chul
    • Transactions of the Korean Society of Pressure Vessels and Piping
    • /
    • v.5 no.1
    • /
    • pp.9-13
    • /
    • 2009
  • The containment local leakage rate testing in nuclear power plants is performed in accordance with ANSI/ANS-56.8(1994) in Korea. Two methods, the make-up flow rate and the pressure decay, are used for LLRT. Though ANSI/ANS-56.8 does not define clearly the minimum test duration for the make-up flow rate method, it requires obtaining the data after reaching the stable condition. Thus the prerequisite stable condition for data acquisition and the test period for type "C" LLRT is differently applied to each NPPs. Therefore, this study presents a unified test criteria for data stabilization and test duration through experiments to improve the test reliability for type "C".

  • PDF

Development of Concrete Material Model for Nonlinear Analysis of Nuclear Containment Building (원전 격납건물 비선형 해석을 위할 콘크리트 재료모델 개발)

  • 이홍표;전영선;서정문;신재철
    • Proceedings of the Computational Structural Engineering Institute Conference
    • /
    • 2004.10a
    • /
    • pp.312-319
    • /
    • 2004
  • This paper is mai y focused to develop new concrete material model such as ultimate failure surface in compression-compression region, hardening rule and cracking criteria which are basically used in the nonlinear finite element analysis of nuclear prestressed concrete containment building. From the Kepri's experimental results, failure surface of the concrete based on the elasto-plastic material model is modified and new cracking criteria is proposed. Nonlinear FE analysis program using a new material model is implemented to analysis plane concrete. Finally, numerical simulation to compare the performance of the new material model with experimental results is employed. The numerical results by the proposed model in this study agree very well with the experimental data.

  • PDF

A Study on Thermal Stress in T/G Wall of Containment Building (격납건물 텐던갤러리 벽체의 온도응력에 대한 연구)

  • 김진근;양은익;박영진;송영철;방기성
    • Proceedings of the Korea Concrete Institute Conference
    • /
    • 1998.04a
    • /
    • pp.193-198
    • /
    • 1998
  • In this study, the change of concrete temperature, strain and thermal stress were measured by using the embedded type concrete gauges in tendon gallery wall of containment building. A finite element analysis was performed to clarify the thermal behavior of concrete. The analytic and test results were investigated to improve the validity of analytic method. According to the test results, concrete temperature, strain and thermal stress were strongly affected by measuring point and environment condition of member. And the thermal stress was developed in the member which was not demoulded at early ages. This is caused by the change of internal temperature and restrained condition. A finite element effectively interpreted the test results by estimating the concrete properties and the site condition.

  • PDF

Efficient Design Procedure of Concrete Dome and Ring Beam in Containment Structures (콘크리트 격납구조물 돔 및 링빔의 효율적인 설계 기법)

  • Jeon, Se-Jin;Kim, Young-Jin
    • Proceedings of the Korea Concrete Institute Conference
    • /
    • 2010.05a
    • /
    • pp.139-140
    • /
    • 2010
  • Combined analysis is required for the concrete dome and ring beam of containment structure due to the interaction in section forces. In this study, an efficient design procedure is proposed that can be used to determine the preliminary sections of the dome and ring beam as well as a proper level of prestress in the ring beam, prior to a detailed design. The procedure applies the membrane theory of the shell of revolution.

  • PDF

Development of Thermal Type Fluid Level Transmitter for Water Level Measurement of Containment Building in Nuclear Power Plant (원자력 발전소 격납 건물의 수위 측정을 위한 열식 레벨 측정기 개발)

  • Yoon, Joon-Yong;Seong, Nak-Won;Lee, Chul-Ho
    • 유체기계공업학회:학술대회논문집
    • /
    • 2001.11a
    • /
    • pp.404-410
    • /
    • 2001
  • A new thermal type fluid level transmitter was designed and tested at the HITROL R&D institute. The relation of heat transfer and electric resistance was adopted as an operation principle. The length of a fabricated level transmitter was two meters and a water under normal temperature was used as a working fluid for the experiment Finally, the new product could have a high precision, acceptable accuracy and reasonable response time. Foreign-made level transmitter of this type is under in use for measuring water level of containment building in nuclear power plants so far. It is expected that new product will substitute it.

  • PDF

A Study on the Two Phase Flow in the Floor of Containment Building after a Loss of Coolant Accident (냉각재 상실사고 후 격납건물내의 이상유동 연구)

  • Bae, Jin-Hyo;Park, Man Heung;Koh, Chul-Kyun;Lee, Jae-Heon
    • Transactions of the Korean Society of Mechanical Engineers B
    • /
    • v.23 no.10
    • /
    • pp.1274-1284
    • /
    • 1999
  • The Regulatory Guide 1.82 recommends an analysis of hydraulic performance for sump of ECCS (Emergency Core Cooing System) when LOCA(Loss of Coolant Accident) occurs in a nuclear power plant. The present study deals with 3-dimensional, unsteady, turbulent and two-phase flow simulation to examine the behavior of mixture of reactor coolant and debris near the floor of containment building in conjunction with appropriate assumptions. The dispersed solid model has been adjusted to the interfacial momentum transfer between reactor coolant and debris. According to the results, the counterclockwiserecirculation zone had been formed in the region between sump and connection aisle about 376 second after LOCA occurs. The debris thickness accumulated on a sump screen periodically increases or decreases up to 2000 second, afterwards its peak decreases.

A Study on the Nonlinear Finite Element Analysis of Prestressed Concrete Containment Vessel (프리스트레스 콘크리트 원전 격납건물의 비선형 유한요소해석에 관한 연구)

  • Lee Hong-Pyo;Choun Young-Sun;Song Young-Chul
    • Proceedings of the Computational Structural Engineering Institute Conference
    • /
    • 2006.04a
    • /
    • pp.639-646
    • /
    • 2006
  • A nonlinear finite element analysis is carried out to predict the ultimate internal pressure and failure mechanism of a 1/4 scale prestressed concrete containment vessel(PCCV) model using the commercial code ABAQUS. Therefore, this paper is mainly focused to compare the influence of concrete material model, tension stiffening parameter, uplift phenomenon and basemat. From the analysis results, nonlinear behavior of the PCCV showed a substantially different aspects in accordance with the nonlinear material model for the concrete as well as tension stiffening parameter. The boundary conditions beneath the basemat are considered to be a fixed condition and a nonlinear spring element to compare the influence of the uplift. The finite element analysis is considered with and without a basemat to find out the influence of the basemant itself. From the analysis results, the nonlinear behavior of the PCCV is entirely similar for the two cases.

  • PDF