• Title/Summary/Keyword: Flow test

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Development of Coolant Flow Simulation System for Nuclear Fuel Test Rigs (핵연료조사리그 냉각수 유동 모의장치 개발)

  • Hong, Jintae;Joung, Chang-Young;Heo, Sung-Ho;Kim, Ka-Hye
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.39 no.1
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    • pp.117-123
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    • 2015
  • To remove heat generated during a burn-up test of nuclear fuels, the heat generation rate of nuclear fuels should be calculated accurately, and a coolant should be circulated in the test loop at an adequate flow rate. HANARO is an open pool-type reactor with an independent test loop for the burn-up test of nuclear fuels. A test rig is installed in the test loop, and a coolant is circulated through the test loop to maintain the temperature of the nuclear fuel rods within a desired temperature during an irradiation test. The components and sensors in the test rig can be broken or malfunction owing to the flow-induced vibration. In this study, a coolant flow simulation system was developed to verify and confirm the soundness of components and sensors assembled in the test rig with a high flow rate of the coolant.

Evaluation of temperatures and flow areas of the Phebus Test FPT0

  • Koji Nishida;Naoki Sano;Seitaro Sakurai;Michio Murase
    • Nuclear Engineering and Technology
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    • v.56 no.3
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    • pp.886-892
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    • 2024
  • The cladding temperatures and axial mass distribution computed by MAAP5 were compared with their measured values in the test bundle of the Phebus Test FPT0. The computed cladding temperatures were in good agreed with the measured values in the pre-transient phase. In the transient heat-up phase, the computed temperatures were overestimated by the Baker-Just correlation in MAAP5, but the computed temperatures could simulate the subsequently measured values. The computed mass distribution in the axial direction was in qualitative agreement with the measured one for post-test fuel damage observations. The calculated flow areas of inner and outer regions in the test bundle were compared with the photographic observations. MAAP5 computed them at the height of 0.2 m where the molten pool formed was in qualitative agreement with the photographic observations. It was found that the remaining steam flow paths might be caused by the gas-liquid two-phase flow counter-current flow limitation.

Hydraulic performance and flow resistance tests of various hydraulic parts for optimal design of a reactor coolant pump for a small modular reactor

  • Byeonggeon Bae;Jaeho Jung;Je Yong Yu
    • Nuclear Engineering and Technology
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    • v.55 no.3
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    • pp.1181-1190
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    • 2023
  • Hydraulic performance and flow resistance tests were performed to confirm the main parameters of the hydraulic instrumentation that can affect the pump performance of the reactor coolant pump. The flow resistance test offers important experimental data, which are necessary to predict the behavior of the primary coolant when the circulation of the reactor coolant pump is stopped. Moreover, the shape of the hydraulic section of the pump, which was considered in the test, was prepared to compare the mixed-flow- and axial-flow-type models, the difference in the number of blades of the impeller and diffuser, the difference in the shape of the impeller blade and its thickness, and the effect of coating at the suction bell. Additionally, five models of the hydraulic part were manufactured for the experiments. In this study, the differences in performance owing to the design factors were confirmed through the experimental results.

Parametric study of porous media as substitutes for flow-diverter stent

  • Ohta, Makoto;Anzai, Hitomi;Miura, Yukihisa;Nakayama, Toshio
    • Biomaterials and Biomechanics in Bioengineering
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    • v.2 no.2
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    • pp.111-125
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    • 2015
  • For engineers, generating a mesh in porous media (PMs) sometimes represents a smaller computational load than generating realistic stent geometries with computer fluid dynamics (CFD). For this reason, PMs have recently become attractive to mimic flow-diverter stents (FDs), which are used to treat intracranial aneurysms. PMs function by introducing a hydraulic resistance using Darcy's law; therefore, the pressure drop may be computed by test sections parallel and perpendicular to the main flow direction. However, in previous studies, the pressure drop parallel to the flow may have depended on the width of the gap between the stent and the wall of the test section. Furthermore, the influence of parameters such as the test section geometry and the distance over which the pressure drops was not clear. Given these problems, computing the pressure drop parallel to the flow becomes extremely difficult. The aim of the present study is to resolve this lack of information for stent modeling using PM and to compute the pressure drop using several methods to estimate the influence of the relevant parameters. To determine the pressure drop as a function of distance, an FD was placed parallel and perpendicular to the flow in test sections with rectangular geometries. The inclined angle method was employed to extrapolate the flow patterns in the parallel direction. A similar approach was applied with a cylindrical geometry to estimate loss due to pipe friction. Additionally, the pressure drops were computed by using CFD. To determine if the balance of pressure drops (parallel vs perpendicular) affects flow patterns, we calculated the flow patterns for an ideal aneurysm using PMs with various ratios of parallel pressure drop to perpendicular pressure drop. The results show that pressure drop in the parallel direction depends on test section. The PM thickness and the ratio of parallel permeability to perpendicular permeability affect the flow pattern in an ideal aneurysm. Based on the permeability ratio and the flow patterns, the pressure drop in the parallel direction can be determined.

Review on Measured Stress and Flow Stress at Room-Temperature Compression Test (상온압축시험에서 측정응력과 유동응력과의 관계고찰)

  • Park J. S.;Lee Y. S.;Lee J. H.
    • Proceedings of the Korean Society for Technology of Plasticity Conference
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    • 2001.05a
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    • pp.13-15
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    • 2001
  • Compression test has been used to measure material flow stress due to limited capability of tensile test at the fast strain rate. Since the frictional stress unavoidable during compression test should be properly eliminated from the measured stress, calibration of the measured stress by using friction factor has been made for the flow stress measurement. Also, calibrated stresses by interrupted and continuous compression tests have been compared with the true stress measured by tensile test at $0.2\%$ carbon steel.

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Review Methods of Pumping Effciency using the Concrete flow Table Test (콘크리트 플로 테이블 테스트를 활용한 압송성 검토 방법)

  • Kwon, Hae-Won;Gong, Min-Ho;Kim, Bong-Sup;Yu, Jong-Jin
    • Proceedings of the Korean Institute of Building Construction Conference
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    • 2016.05a
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    • pp.9-10
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    • 2016
  • This study is purposed to review the confirm method of pumping efficiency using the concrete flow table test in Korea environment. This test method is registered as the "EN 12350-5, Testing fresh concrete. Flow table test" in Eurocode. When applying this test in the Korea construction environment, we reviewed that reasonably apply on the Korean construction Environment. As a result, test results analysis showed that the reality looks a big difference. Its cause is believed to be due to the shape of coarse & fine aggregate. But it will be better predict method, through the correlation analysis of construction data and the standard(Placing Concrete by pumping Methods(ACI Manual of concrete Practice 304.2R-96)).

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Cross Flow Characteristics of the Core Simulator in SMART Reactor Flow Distribution Test Facility (SMART 유동분포시험장치 노심모의기에서의 횡방향 유동 특성)

  • Yoon, Jung;Kim, Young-In;Chung, Young-Jong;Lee, Won-Jae
    • The KSFM Journal of Fluid Machinery
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    • v.15 no.4
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    • pp.5-11
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    • 2012
  • To identify the flow characteristics of the SMART reactor, a flow distribution model test and a numerical simulation are performed in KAERI. Among several part of the SMART reactor, the fuel assemblies are simulated using simulators because of the complexity. The geometries of the core in the SMART reactor and simulator are different, but some similarities are maintained such as the ratio of pressure drop in the vertical and cross directions. There are cross flow holes in each core simulator to reproduce the cross flow of SMART fuel assemblies. To know the flow characteristics of the cross flow, numerical analysis is performed. As the cross flow area is decreased, the pressure drop between inlet and outlet is decreased. Also, when the flow imbalance between two core simulators is constant, the cross flow area does not significantly affect the cross flow.

Performance Study on the Supersonic Diffuser Contraction Ratio of High-Altitude Test Facility for Hypersonic Propulsion (극초음속 추진기관 고공환경 시험장치의 이차목 디퓨저 수축비에 따른 성능연구)

  • Lee, Seongmin;Shin, Donghae;Shin, Mingyu;Ko, Youngsung;Kim, Sunjin;Lee, Jungmin
    • Proceedings of the Korean Society of Propulsion Engineers Conference
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    • 2017.05a
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    • pp.1026-1030
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    • 2017
  • In this study, we propose an supersonic diffuser that is one of test facilities for hypersonic propulsion engine, and conduct numerical analyses and cold flow test using each diffuser as the corresponding variable. Specifically, inner flow characteristics are computed based on mach number and pressure by the numerical analyses. Also, we test through cold flow test the pressure in the vacuum chamber and the inner pressure that is formed by the wall pressure. Finally, we compare the results from cold flow test and the numerical analyses, and report a preliminary result that might be useful to construct a better test facility of hypersonic propulsion engine in the future.

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A Review on the Regionalization Methodology for Core Inlet Flow Distribution Map

  • Lee, Byung-Jin;Jang, Ho-Cheol;Cheong, Jong-Sik;Baik, Se-Jin;Park, Young-Sheop
    • Nuclear Engineering and Technology
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    • v.33 no.4
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    • pp.441-456
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    • 2001
  • ABB-CE's regionalization methodology for the core inlet flow distribution map is reviewed. This methodology merges the test data of fuel assembly locations which are either in symmetry or strongly correlated with others. It increases the number of available test data for each regional flow factor It makes up effectively for the deficiency due to limited number of test data. It also contributes to making the core inlet flow distribution smoother not only locally but also over the entire core, and to relieving the impacts of test errors that may happen due to some do- calibrated local pressure measurement taps. As a result, the core inlet How distribution data becomes more statistically useful and thus the conservatism involved in handling the core inlet flow factors for the thermal margin analysis is expected to be reduced. Meanwhile, the regionalized map may lose the unique local characteristics in core inlet flow distribution too much. By an alternative approach introduced in the present work, it is shown that such a disadvantage can be mitigated somewhat if the engineering judgement is made more

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Development of an Ultrasonic Gas Flow Meter Using Transit Time Difference (전달 시간차 방식 초음파 가스 유량계)

  • 박상국;황원호
    • Journal of Institute of Control, Robotics and Systems
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    • v.9 no.9
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    • pp.707-713
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    • 2003
  • We investigate the ultrasonic gas flow meter for the measurement of gas volume quantity, which passing through pipe, using the transit time difference method. We have designed a receiving system of an ultrasonic signal and hardware system of a flow meter Also, we have designed an experimental system for the characteristic test and calibration of a gas flow meter system. We have developed an ultrasonic gas flow meter, which has a measurement uncertainty within $\pm$ 1.7 %. For the test, we have compared our system with a difference pressure type flow meter for a few months in the real field. Through the test, we have confirmed that our system have a good reliability and durability. Also, we have confirmed that our system follows very well the variation of gas volume quantity, which was measured by a difference pressure type flow meter.