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1
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Bello S, Gao P, Abiodun Olatubosun S, Lin Y, Njoroge J. Experimental study of heat distribution in a Non-uniform heat source of a natural circulation loop. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109076] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
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Analysis of the natural circulation flow map uncertainties in an integral small modular reactor. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111156] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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Xu Y, Peng M, Xia G, Shang H. Optimization of forced circulation to natural circulation transition characteristics of IPWR. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108249] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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4
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Closed-loop experimental investigation of single-phase natural circulation flow phenomena based on temperature and heating power variations. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2020.107809] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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5
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Experimental and numerical investigations on effect of reverse flow on transient from forced circulation to natural circulation. NUCLEAR ENGINEERING AND TECHNOLOGY 2020. [DOI: 10.1016/j.net.2020.02.019] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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Pilehvar A, Esteki M, Ansarifar G, Hedayat A. Stability analysis and parametric study of natural circulation integrated self-pressurized water reactor. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2019.107279] [Citation(s) in RCA: 8] [Impact Index Per Article: 2.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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7
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Saeed HA, Wang H, Peng M, Hussain A, Nawaz A. Online fault monitoring based on deep neural network & sliding window technique. PROGRESS IN NUCLEAR ENERGY 2020. [DOI: 10.1016/j.pnucene.2019.103236] [Citation(s) in RCA: 18] [Impact Index Per Article: 4.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/01/2022]
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Saeed HA, Peng MJ, Wang H, Zhang BW. Novel fault diagnosis scheme utilizing deep learning networks. PROGRESS IN NUCLEAR ENERGY 2020. [DOI: 10.1016/j.pnucene.2019.103066] [Citation(s) in RCA: 22] [Impact Index Per Article: 5.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
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9
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Liu W, Wang L, Zhou T, Zhang G, Bai Y. Transient characteristics analysis of lead-based reactor from forced circulation to natural circulation. PROGRESS IN NUCLEAR ENERGY 2019. [DOI: 10.1016/j.pnucene.2019.103052] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Li R, Xia G, Peng M, Sun L. The simulation study on natural circulation operating characteristics of FNPP in inclined condition. NUCLEAR ENGINEERING AND TECHNOLOGY 2019. [DOI: 10.1016/j.net.2019.05.021] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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11
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Reliability assessment of passive residual heat removal system of IPWR using Kriging regression model. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2018.12.040] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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Zhu H, Zhang S, Xia G, Peng M. Analysis of operating characteristics of IPWR under natural circulation. KERNTECHNIK 2018. [DOI: 10.3139/124.110942] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
Abstract
AbstractMany integrated pressurized water reactor (IPWR) designs using natural circulation operation mainly to enhance their inherent safety. The operating characteristics of primary coolant are completely different without mechanical pumps. The designs and safety analysis of forced circulation reactors are widely researched, but the natural circulation characteristics of IPWR have not been well studied by literatures. The present work discussed the thermal-hydraulic characteristics of IPWR under natural circulation conditions by using the best estimate codes RELAP5. And the effect of system parameters on natural circulation characteristics of IPWR is also studied. The results show that, the primary coolant average temperature and steam pressure are two key parameters that affect the natural circulation stable operating load. The set value of primary coolant average temperature effects the core outlet temperature and the steam temperature, but the primary coolant flow is basically the same under different primary coolant average temperature but same load conditions. The smaller steam pressure is more conducive to produce superheated steam, but there is risk of two phase flow instability in OTSG secondary side. The rapid load change process under natural circulation indicating that the reactor has a good load tracking characteristics under natural circulation, but the rapid change of primary coolant temperature will cause oscillations in system parameters.
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Affiliation(s)
- H. Zhu
- 1Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin City 150001, China
| | - S. Zhang
- 2School of Energy and Power Engineering, Beijing University of Aeronautics and Astronautics, Beijing 100191, China
| | - G. Xia
- 1Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin City 150001, China
| | - M. Peng
- 1Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin City 150001, China
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Neutronic/thermal-hydraulic coupling analysis of natural circulation IPWR under ocean conditions. ANN NUCL ENERGY 2018. [DOI: 10.1016/j.anucene.2017.10.043] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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He L, Wang B, Xia G, Peng M. Study on natural circulation characteristics of an IPWR under inclined and rolling condition. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.03.033] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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