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Zhang T, Brooks CS. Stability Tests and Analysis of a Low-Pressure Natural Circulation Loop with Flashing Instability. NUCL TECHNOL 2023. [DOI: 10.1080/00295450.2022.2151823] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 02/09/2023]
Affiliation(s)
- Taiyang Zhang
- University of Illinois at Urbana-Champaign, Department of Nuclear, Plasma, and Radiological Engineering, Urbana, Illinois 61801
| | - Caleb S. Brooks
- University of Illinois at Urbana-Champaign, Department of Nuclear, Plasma, and Radiological Engineering, Urbana, Illinois 61801
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2
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Qi X, Zhao Z, Ai P, Chen P, Sun Z, Meng Z. Experiment investigation on flow characteristics of open natural circulation system. NUCLEAR ENGINEERING AND TECHNOLOGY 2022. [DOI: 10.1016/j.net.2021.11.012] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
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3
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Bertani C, Bersano A, De Salve M, Sobrero G. Experimental analysis of the start-up of a natural circulation loop in single and two-phase flow. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111532] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
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4
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Zhang T, Brooks CS. Linear stability analysis of flashing instability based on the homogeneous equilibrium model. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2020.110994] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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5
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Bang J, Jerng DW, Kim H. Comparisons of performance and operation characteristics for closed- and open-loop passive containment cooling system design. NUCLEAR ENGINEERING AND TECHNOLOGY 2021. [DOI: 10.1016/j.net.2021.01.039] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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6
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Sun J, Deng J, Ran X, Ding M, Fan G. Experimental study on flow modes and transient characteristics in low-pressure equal-height-difference natural circulation system. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2020.107965] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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7
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Olatubosun SA. Numerical approach for estimating the conditions for natural circulation in a simple nuclear passive system. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107350] [Citation(s) in RCA: 8] [Impact Index Per Article: 2.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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8
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Saikia K, Basu DN, Pandey M. Parametric studies on startup transients in multiple parallel channels of a natural circulation boiling system. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2019.107211] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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9
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Lim SG, No HC, Lee SW, Kim HG, Cheon J, Lee JM, Ohk SM. Development of stability maps for flashing-induced instability in a passive containment cooling system for iPOWER. NUCLEAR ENGINEERING AND TECHNOLOGY 2020. [DOI: 10.1016/j.net.2019.06.026] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
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10
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Ooi ZJ, Kumar V, Brooks CS. Experimental database of two-phase natural circulation with local measurements. PROGRESS IN NUCLEAR ENERGY 2019. [DOI: 10.1016/j.pnucene.2019.04.003] [Citation(s) in RCA: 14] [Impact Index Per Article: 2.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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11
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Tompkins C, Corradini M. Flow pattern transition instabilities in a natural circulation cooling facility. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2018.03.018] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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12
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13
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Hou X, Sun Z, Lei W. Capability of RELAP5 code to simulate the thermal-hydraulic characteristics of open natural circulation. ANN NUCL ENERGY 2017. [DOI: 10.1016/j.anucene.2017.06.010] [Citation(s) in RCA: 32] [Impact Index Per Article: 4.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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14
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Castillo R, Alonso G, Ramirez R, Martinez E. An alternative method for local surveillance of coolant flow in BWRs fuel channels. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.04.030] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
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16
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Auban O, Paladino D, Zboray R. Experimental Investigation of Natural-Circulation Flow Behavior under Low-Power/Low-Pressure Conditions in the Large-Scale PANDA Facility. NUCL TECHNOL 2017. [DOI: 10.13182/nt04-a3568] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Olivier Auban
- Paul Scherrer Institut, Nuclear Energy and Safety Department Laboratory for Thermal-Hydraulics, 5232 Villigen PSI, Switzerland
| | - Domenico Paladino
- Paul Scherrer Institut, Nuclear Energy and Safety Department Laboratory for Thermal-Hydraulics, 5232 Villigen PSI, Switzerland
| | - Robert Zboray
- Paul Scherrer Institut, Nuclear Energy and Safety Department Laboratory for Thermal-Hydraulics, 5232 Villigen PSI, Switzerland
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Hu R, Kazimi MS. Flashing-Induced Instability Analysis and the Start-Up of Natural Circulation Boiling Water Reactors. NUCL TECHNOL 2017. [DOI: 10.13182/nt11-a12542] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.9] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Rui Hu
- Massachusetts Institute of Technology, Center for Advanced Nuclear Energy Systems Nuclear Science and Engineering Department, 77 Massachusetts Avenue Cambridge, Massachusetts 02139
| | - Mujid S. Kazimi
- Massachusetts Institute of Technology, Center for Advanced Nuclear Energy Systems Nuclear Science and Engineering Department, 77 Massachusetts Avenue Cambridge, Massachusetts 02139
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Demazière C, Marcel C, Rohde M, van der Hagen T. Multifractal Analysis of Chaotic Flashing-Induced Instabilities in Boiling Channels in the Natural-Circulation CIRCUS Facility. NUCL SCI ENG 2017. [DOI: 10.13182/nse08-a2745] [Citation(s) in RCA: 12] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Christophe Demazière
- Chalmers University of Technology, Department of Nuclear Engineering, SE-412 96 Göteborg, Sweden
| | - Christian Marcel
- Delft University of Technology, Department of Physics of Nuclear Reactors, Delft, 2629 BJ, The Netherlands
| | - Martin Rohde
- Delft University of Technology, Department of Physics of Nuclear Reactors, Delft, 2629 BJ, The Netherlands
| | - Tim van der Hagen
- Delft University of Technology, Department of Physics of Nuclear Reactors, Delft, 2629 BJ, The Netherlands
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Manera A, Prasser HM, van der Hagen THJJ. Suitability of Drift-Flux Models, Void-Fraction Evolution, and 3-D Flow Pattern Visualization During Stationary and Transient Flashing Flow in a Vertical Pipe. NUCL TECHNOL 2017. [DOI: 10.13182/nt05-3] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.9] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Annalisa Manera
- Delft University of Technology, Interfaculty Reactor Institute Mekelweg 15, 2629 JB, Delft, The Netherlands and Forschungszentrum Rossendorf Institute of Safety Research, P.O. Box 510119, D-01314, Dresden, Germany
| | - Horst-Michael Prasser
- Forschungszentrum Rossendorf Institute of Safety Research, P.O. Box 510119, D-01314, Dresden, Germany
| | - Tim H. J. J. van der Hagen
- Delft University of Technology Interfaculty Reactor Institute, Mekelweg 15, 2629 JB, Delft, The Netherlands
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Rabiee A, Mirzaee MM, Nematollahi MR, Atf A. Experimental and numerical investigation of natural circulation stability of the SHUNCL thermal-hydraulic loop. PROGRESS IN NUCLEAR ENERGY 2016. [DOI: 10.1016/j.pnucene.2016.09.011] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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21
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Phung VA, Kööp K, Grishchenko D, Vorobyev Y, Kudinov P. Automation of RELAP5 input calibration and code validation using genetic algorithm. NUCLEAR ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.nucengdes.2016.01.003] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
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22
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Simulating investigations on the start-up of the open natural circulation system. NUCLEAR ENGINEERING AND DESIGN 2015. [DOI: 10.1016/j.nucengdes.2015.03.021] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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23
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Input Calibration and Validation of RELAP5 Against CIRCUS-IV Single Channel Tests on Natural Circulation Two-Phase Flow Instability. SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS 2015. [DOI: 10.1155/2015/130741] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
Abstract
RELAP5 is a system thermal-hydraulic code that is used to perform safety analysis on nuclear reactors. Since the code is based on steady state, two-phase flow regime maps, there is a concern that RELAP5 may provide significant errors for rapid transient conditions. In this work, the capability of RELAP5 code to predict the oscillatory behavior of a natural circulation driven, two-phase flow at low pressure is investigated. The simulations are compared with a series of experiments that were performed in the CIRCUS-IV facility at the Delft University of Technology. For this purpose, we developed a procedure for calibration of the input and code validation. The procedure employs (i) multiple parameters measured in different regimes, (ii) independent consideration of the subsections of the loop, and (iii) assessment of importance of the uncertain input parameters. We found that predicted system parameters are less sensitive to variations of the uncertain input and boundary conditions in high frequency oscillations regime. It is shown that calculation results overlap experimental values, except for the high frequency oscillations regime where the maximum inlet flow rate was overestimated. This finding agrees with the idea that steady state, two-phase flow regime maps might be one of the possible reasons for the discrepancy in case of rapid transients in two-phase systems.
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Prediction of Flow Regimes and Thermal Hydraulic Parameters in Two-Phase Natural Circulation by RELAP5 and TRACE Codes. SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS 2015. [DOI: 10.1155/2015/296317] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
Abstract
In earlier study we have demonstrated that RELAP5 can predict flow instability parameters (flow rate, oscillation period, temperature, and pressure) in single channel tests in CIRCUS-IV facility. The main goals of this work are to (i) validate RELAP5 and TRACE capabilities in prediction of two-phase flow instability and flow regimes and (ii) assess the effect of improvement in flow regime identification on code predictions. Most of the results of RELAP5 and TRACE calculation are in reasonable agreement with experimental data from CIRCUS-IV. However, both codes misidentified instantaneous flow regimes which were observed in the test with high speed camera. One of the reasons for the incorrect identification of the flow regimes is the small tube flow regime transition model in RELAP5 and the combined bubbly-slug flow regime in TRACE. We found that calculation results are sensitive to flow regime boundaries of RELAP5 which were modified in order to match the experimental data on flow regimes. Although the flow regime became closer to the experimental one, other predicted thermal hydraulic parameters showed larger discrepancy with the experimental data than with the base case calculations where flow regimes were misidentified.
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Lakshmanan S, Pandey M. Numerical investigations on power ramping procedure for a natural circulation boiling water reactor. NUCLEAR ENGINEERING AND DESIGN 2010. [DOI: 10.1016/j.nucengdes.2009.12.011] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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26
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Numerical Investigation of Startup Instabilities in Parallel-Channel Natural Circulation Boiling Systems. SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS 2010. [DOI: 10.1155/2010/574195] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
Abstract
The behaviour of a parallel-channel natural circulation boiling water reactor under a low-pressure low-power startup condition has been studied numerically (using RELAP5) and compared with its scaled model. The parallel-channel RELAP5 model is an extension of a single-channel model developed and validated with experimental results. Existence of in-phase and out-of-phase flashing instabilities in the parallel-channel systems is investigated through simulations under equal and unequal power boundary conditions in the channels. The effect of flow resistance on Type-I oscillations is explored. For nonidentical condition in the channels, the flow fluctuations in the parallel-channel systems are found to be out-of-phase.
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Lakshmanan S, Pandey M. Analysis of startup oscillations in natural circulation boiling systems. NUCLEAR ENGINEERING AND DESIGN 2009. [DOI: 10.1016/j.nucengdes.2009.06.017] [Citation(s) in RCA: 11] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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28
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Study of startup transients and power ramping of natural circulation boiling systems. NUCLEAR ENGINEERING AND DESIGN 2009. [DOI: 10.1016/j.nucengdes.2009.01.002] [Citation(s) in RCA: 20] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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29
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Natural Circulation Characteristics at Low-Pressure Conditions through PANDA Experiments and ATHLET Simulations. SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS 2008. [DOI: 10.1155/2008/874969] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
Abstract
Natural circulation characteristics at low pressure/low power have been studied by performing experimental investigations and numerical simulations. The PANDA large-scale facility was used to provide valuable, high quality data on natural circulation characteristics as a function of several parameters and for a wide range of operating conditions. The new experimental data allow for testing and improving the capabilities of the thermal-hydraulic computer codes to be used for treating natural circulation loops in a range with increased attention. This paper presents a synthesis of a part of the results obtained within the EU-Project NACUSP “natural circulation and stability performance of boiling water reactors.” It does so by using the experimental results produced in PANDA and by showing some examples of numerical simulations performed with the thermal-hydraulic code ATHLET.
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Durga Prasad GV, Pandey M, Kalra MS. Review of research on flow instabilities in natural circulation boiling systems. PROGRESS IN NUCLEAR ENERGY 2007. [DOI: 10.1016/j.pnucene.2007.06.002] [Citation(s) in RCA: 75] [Impact Index Per Article: 4.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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31
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Furuya M, Inada F, van der Hagen T. Flashing-induced density wave oscillations in a natural circulation BWR—mechanism of instability and stability map. NUCLEAR ENGINEERING AND DESIGN 2005. [DOI: 10.1016/j.nucengdes.2005.01.006] [Citation(s) in RCA: 70] [Impact Index Per Article: 3.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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