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Development of PWR lower head failure model for severe accident analysis. NUCLEAR ENGINEERING AND DESIGN 2023. [DOI: 10.1016/j.nucengdes.2022.112142] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/31/2022]
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Peng C, Song Y, Deng J, Mao S, Wu J. Numerical Investigation on the Thermal-Hydraulic Characteristics near a Corroded Lower Head of the Reactor Vessel During IVR-ERVC. NUCL SCI ENG 2022. [DOI: 10.1080/00295639.2022.2143208] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 12/24/2022]
Affiliation(s)
- Cheng Peng
- Shanghai University of Electric Power, College of Energy and Mechanical Engineering, Shanghai, China
| | - Youya Song
- Shanghai University of Electric Power, College of Energy and Mechanical Engineering, Shanghai, China
| | - Jian Deng
- Nuclear Power Institute of China, Science and Technology on Reactor System Design Technology Laboratory, Chengdu, China
| | - Sen Mao
- Shanghai University of Electric Power, College of Energy and Mechanical Engineering, Shanghai, China
| | - Jiang Wu
- Shanghai University of Electric Power, College of Energy and Mechanical Engineering, Shanghai, China
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Li Z, Chang H, Chen L, Han K, Fang F. Simulation model for investigating safety margin of three-layer molten pool after late phase in-vessel water injection. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104448] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/07/2022]
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4
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Park JM, Lim K. Multi-dimensional finite element analyses of OECD lower head failure tests. NUCLEAR ENGINEERING AND TECHNOLOGY 2022. [DOI: 10.1016/j.net.2022.08.015] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/15/2022]
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Xue B, Yang Y, Liang T, Chen B, Ma Y, Liu K, Shan H, Kang T, Gu P. Experimental study of stratification behavior of the steady two-liquid corium pool. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.111727] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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Liu L, Deng J, Zhang M, Chen L, Xu Y, Luo Y, Li Y, Sun H, Yu H, Gong H. Analysis of 3-layer corium pool models in CISER2.0 code. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104128] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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Duan G, Yamaji A, Sakai M. A multiphase MPS method coupling fluid–solid interaction/phase-change models with application to debris remelting in reactor lower plenum. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2021.108697] [Citation(s) in RCA: 4] [Impact Index Per Article: 2.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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Effect of different conditions on heat transfer characteristics of molten Zr-Stainless steel pool with water injection. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111467] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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Li Z, Chang H, Fang F, Han K, Chen L, Hao B. Investigation of water injection on molten Zirconium-Stainless steel pool in IVR strategy. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108475] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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Jung J, Kim HY, An SM. Development of the Penetration Tube Failure Analysis Program in the Lower Head of the Reactor Vessel During a Severe Accident. NUCL TECHNOL 2021. [DOI: 10.1080/00295450.2021.1929769] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
Affiliation(s)
- J. Jung
- Korea Atomic Energy Research Institute, Accident Monitoring and Mitigation Research Team, Daejeon 34057, Korea
| | - H. Y. Kim
- Korea Atomic Energy Research Institute, Accident Monitoring and Mitigation Research Team, Daejeon 34057, Korea
| | - S. M. An
- Korea Atomic Energy Research Institute, Accident Monitoring and Mitigation Research Team, Daejeon 34057, Korea
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11
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Heat transfer of film boiling on the molten metal after water injection. PROGRESS IN NUCLEAR ENERGY 2021. [DOI: 10.1016/j.pnucene.2021.103873] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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12
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Development of MPS method and analytical approach for investigating RPV debris bed and lower head interaction in 1F Units-2 and 3. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111244] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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Wang H, Villanueva W, Chen Y, Kulachenko A, Bechta S. Thermo-mechanical behavior of an ablated reactor pressure vessel wall in a Nordic BWR under in-vessel core melt retention. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111196] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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Zhou Z, Gao Y, Hsieh HE, Miao H, Zhang Z. Experimental investigation on pool boiling for downward facing heating with different concentrations of Al2O3 nanofluids. KERNTECHNIK 2021. [DOI: 10.1515/kern-2020-0090] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
Abstract
Abstract
An experimental study has been conducted to examine the effect of different concentrations of α-Al2O3 nanofluids on boiling heat transfer for downward facing heating. The experimental results indicated that the surface heat transfer was enhanced with the rise of the nanofluids concentration, due to the bubble generation rate and disturbance increased. For downward facing heating, bubbles were not able to escape since the bouncy force influenced, and the vapor film appeared earlier as the increase of bubble generation rate. However, the heat transfer coefficient remains at a relatively high value in the early stage of film boiling, which suppresses the deterioration of heat transfer, due to the influences of nanofluids. As the various concentrations of nanofluids increased from 0 g/L to 0.012 g/L, it was found that the enhancement of the CHF (critical heat flux) up to 20.5%. After the nanofluids boiling, the surface roughness decreased and the wettability became worse. From the experimental phenomena, under the influence of these two factors, the bubble activity was enhanced.
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Affiliation(s)
- Z. Zhou
- College of Energy Xiamen University No. 4221-104 Xiang’an South Road Xiamen P.R. China
| | - Y. Gao
- College of Energy Xiamen University No. 4221-104 Xiang’an South Road Xiamen P.R. China
| | - H.-E. Hsieh
- College of Energy Xiamen University No. 4221-104 Xiang’an South Road Xiamen P.R. China
| | - H. Miao
- College of Energy Xiamen University No. 4221-104 Xiang’an South Road Xiamen P.R. China
| | - Z. Zhang
- College of Energy Xiamen University No. 4221-104 Xiang’an South Road Xiamen P.R. China
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Zhou Y, Zhang Y, Zhang K, Wu S, Yu Z, Tian W, Qiu S, Su G. Experimental study on natural convection heat transfer in a two-layer corium pool based on COPRA facility. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2019.04.031] [Citation(s) in RCA: 10] [Impact Index Per Article: 2.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Prasad SV, Nayak AK. Experimental Study on Melt Coolability Capability of Calandria Vault Water During Severe Accident in Indian PHWRs for Prolonged Duration. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2018. [DOI: 10.1115/1.4039636] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
Abstract
The present experimental investigation in a scaled facility of an Indian pressurized heavy water reactors (PHWRs) is focused on the heat transfer behavior from the calandria vessel (CV) to the calandria vault during a prolonged severe accident condition in the presence of decay heat. The transient heat transfer simulates the conditions from single phase to boiling in the calandria vault water, partial uncovery of the CV due to boil off of water in the vault, and refill of calandria vault. Molten borosilicate glass was used as the simulant due to its comparable heat transfer characteristics similar to prototypic material. About 60 kg of the molten material was poured into the test section at about 1100 °C. Decay heat in the melt pool was simulated by using high watt cartridge type heaters. The temperature distributions inside the molten pool across the CV wall thickness and vault water were measured for prolonged period which can be divided into various phases, viz., single phase natural convection heat transfer in calandria vault, boiling heat transfer in calandria vault, partial uncovery of CV, and refilling calandria vault. Experimental results showed that once the crust formed, the inner vessel temperature remained very low and vessel integrity maintained. Even boiling of calandria vault water and uncovery of CV had negligible effect on melt, CV, and vault water temperature. The heat transfer coefficients on outer vessel surface were obtained and compared with various conditions.
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Affiliation(s)
- Sumit V. Prasad
- Homi Bhabha National Institute, Anushaktinagar, Mumbai 400094, India; Reactor Engineering Division, Bhabha Atomic Research Centre, Mumbai 400085, India e-mail:
| | - A. K. Nayak
- Homi Bhabha National Institute, Anushaktinagar, Mumbai 400094, India; Reactor Engineering Division, Bhabha Atomic Research Centre, Mumbai 400085, India e-mail:
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Loktionov V, Mukhtarov E, Lyubashevskaya I. Features of heat and deformation behavior of a VVER-600 reactor pressure vessel under conditions of inverse stratification of corium pool and worsened external vessel cooling during the severe accident. Part 2. Creep deformation and failure of the reactor pressure vessel. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2017.12.018] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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20
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Jianfeng M, Xiangqing L, Shiyi B, Lijia L, Zengliang G. Investigation on multilayer failure mechanism of RPV with a high temperature gradient from core meltdown scenario. NUCLEAR ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.nucengdes.2016.10.005] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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21
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Mao J, Zhu J, Bao S, Luo L, Gao Z. Study on structural failure of RPV with geometric discontinuity under severe accident. NUCLEAR ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.nucengdes.2016.07.027] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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22
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Prasad SV, Nayak AK. Experimental investigation of heat transfer during severe accident of a Pressurized Heavy Water Reactor with simulated decay heat generation in molten pool inside calandria vessel. NUCLEAR ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.nucengdes.2016.03.027] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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23
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A two dimensional approach for temperature distribution in reactor lower head during severe accident. ANN NUCL ENERGY 2015. [DOI: 10.1016/j.anucene.2015.04.042] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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24
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He H, Pan LM, Wu Y, Chen DQ. An analytic model of pool boiling critical heat flux on an immerged downward facing curved surface. NUCLEAR ENGINEERING AND DESIGN 2015. [DOI: 10.1016/j.nucengdes.2015.04.012] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
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25
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Prasad SV, Nayak AK, Kulkarni PP, Vijayan PK, Vaze KK. Study on heat removal capability of calandria vault water from molten corium in calandria vessel during severe accident of a PHWR. NUCLEAR ENGINEERING AND DESIGN 2015. [DOI: 10.1016/j.nucengdes.2014.12.014] [Citation(s) in RCA: 12] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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26
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Zhang L, Zhou Y, Zhang Y, Tian W, Qiu S, Su G. Natural convection heat transfer in corium pools: A review work of experimental studies. PROGRESS IN NUCLEAR ENERGY 2015. [DOI: 10.1016/j.pnucene.2014.11.021] [Citation(s) in RCA: 46] [Impact Index Per Article: 5.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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Experimental study of the fracture kinetics of a tubular 16MnNiMo5 steel specimen under biaxial loading at 900 and 1000°C. Application to the rupture of a vessel bottom head during a core meltdown accident in a pressurized water reactor. NUCLEAR ENGINEERING AND DESIGN 2011. [DOI: 10.1016/j.nucengdes.2011.01.026] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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28
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Tarabelli D, Ratel G, Pélisson R, Guillard G, Barnak M, Matejovic P. ASTEC application to in-vessel corium retention. NUCLEAR ENGINEERING AND DESIGN 2009. [DOI: 10.1016/j.nucengdes.2009.02.021] [Citation(s) in RCA: 9] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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29
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Modelling of PWR lower head failure under severe accident loading using improved shells of revolution theory. NUCLEAR ENGINEERING AND DESIGN 2008. [DOI: 10.1016/j.nucengdes.2008.03.006] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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30
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Study of tearing behaviour of a PWR reactor pressure vessel lower head under severe accident loadings. NUCLEAR ENGINEERING AND DESIGN 2008. [DOI: 10.1016/j.nucengdes.2008.03.005] [Citation(s) in RCA: 13] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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31
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Sehgal BR. Stabilization and termination of severe accidents in LWRs. NUCLEAR ENGINEERING AND DESIGN 2006. [DOI: 10.1016/j.nucengdes.2006.03.040] [Citation(s) in RCA: 22] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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32
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Esmaili H, Khatib-Rahbar M. Analysis of likelihood of lower head failure and ex-vessel fuel coolant interaction energetics for AP1000. NUCLEAR ENGINEERING AND DESIGN 2005. [DOI: 10.1016/j.nucengdes.2005.02.003] [Citation(s) in RCA: 36] [Impact Index Per Article: 1.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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