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Tranchida J, Nicaud F, Beeler BW, Bourasseau E. Thermophysical properties and unexpected viscosity of liquid (U, Zr): An atomistic investigation. J Chem Phys 2024; 160:214507. [PMID: 38836454 DOI: 10.1063/5.0203177] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 02/10/2024] [Accepted: 04/22/2024] [Indexed: 06/06/2024] Open
Abstract
In this study, we performed a numerical investigation of the thermophysical properties of liquid (U, Zr) mixtures, which are particularly relevant in the context of hypothetical nuclear accidents and the formation of in-vessel coriums. To do so, atomistic simulations leveraging classical molecular dynamics and an interatomic potential developed for solid (U, Zr) structures are performed. Our methodology is first validated by comparing the predictions of our model for the melting temperature and the structure factors to experimental, phase diagram, and ab initio data. We then use the approach to evaluate the temperature and composition dependence of four fundamental properties in the context of coriums: density, heat capacity, compressibility, and viscosity. Systematic comparisons to the existing experimental data are performed and discussed. In particular, the viscosity of liquid (U, Zr) mixtures is investigated by comparing diffusion calculations and the Stokes-Einstein formula as well as the results obtained with the Green-Kubo methodology, empirical predictions, and experimental data. Notably, the viscosity of the mixtures is predicted to be significantly higher than that of the single-element liquids, which is unexpected and could have crucial consequences on the early stages of the formation and flow of in-vessel corium.
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Affiliation(s)
- J Tranchida
- DES, IRESNE, DEC, CEA Cadarache, Saint-Paul-Lez-Durance 13108, France
| | - F Nicaud
- DES, IRESNE, DEC, CEA Cadarache, Saint-Paul-Lez-Durance 13108, France
| | - B W Beeler
- Department of Nuclear Engineering, North Carolina State University, Raleigh, North Carolina 27695, USA
- Idaho National Laboratory, Idaho Falls, Idaho 83415, USA
| | - E Bourasseau
- DES, IRESNE, DEC, CEA Cadarache, Saint-Paul-Lez-Durance 13108, France
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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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3
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Wang H, Villanueva W. Structural behavior of an ablated reactor pressure vessel wall with external cooling. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104446] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/31/2022]
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Park JS, Park HK, Chung BJ. Influence of an in-vessel debris bed on the heat load to a reactor vessel under an IVR condition. NUCLEAR ENGINEERING AND TECHNOLOGY 2022. [DOI: 10.1016/j.net.2022.09.023] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/14/2022]
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Li Z, Chang H, Chen L, Han K, Fang F. Heat transfer experiment with the prototypical Ra number of heavy metallic layer in IVR strategy. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104152] [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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Mechanistic critical heat flux prediction for in-vessel retention conditions. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111494] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
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Park RJ, Son D, Kang HS, An SM, Ha KS. Development of IVR-ERVC evaluation method and its application to the SMART. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108463] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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Rafiq Akand M, Kitahara K, Matsumoto T, Liu W, Morita K. Experimental study and modeling of bubble lift-off diameter in subcooled flow boiling including the inclination effect of the heating surface. J NUCL SCI TECHNOL 2021. [DOI: 10.1080/00223131.2021.1931518] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
Affiliation(s)
- M.A. Rafiq Akand
- Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University, Fukuoka, Japan
| | - Kei Kitahara
- Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University, Fukuoka, Japan
| | - Tatsuya Matsumoto
- Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University, Fukuoka, Japan
| | - Wei Liu
- Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University, Fukuoka, Japan
| | - Koji Morita
- Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University, Fukuoka, Japan
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Investigation of the pressure vessel lower head potential failure under IVR-ERVC condition during a severe accident scenario in APR1400 reactors. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111107] [Citation(s) in RCA: 8] [Impact Index Per Article: 2.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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Song MW, Yeo D, No HC. Modeling of in-vessel gap cooling and its validation against LAVA, ALPHA, and LMP200 experiments. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2020.111028] [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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Merzari E, Cheung FB, Bajorek SM, Hassan Y. 40th Anniversary of the first international topical meeting on nuclear reactor thermal-hydraulics: Highlights of thermal-hydraulics research in the past four decades. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2020.110965] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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Song MW, NO HC, Kim J, Kim M, Yeo D, Yoon SH, Yoon HJ. Modeling of annular gap thickness formed by interaction between corium and water in lower head of reactor vessel. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110841] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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Development of multi-cell flows in the three-layered configuration of oxide layer and their influence on the reactor vessel heating. NUCLEAR ENGINEERING AND TECHNOLOGY 2019. [DOI: 10.1016/j.net.2019.02.004] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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The comprehensive analysis of coolability limits of passive external reactor vessel cooling under in-vessel retention. ANN NUCL ENERGY 2018. [DOI: 10.1016/j.anucene.2018.05.048] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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Kim SH, Chung BJ. Mass transfer experiments on the natural convection heat transfer of the oxide pool in a three-layer configuration. PROGRESS IN NUCLEAR ENERGY 2018. [DOI: 10.1016/j.pnucene.2018.02.022] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/17/2022]
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Hu Q, Yan X, Huang S, Yu J. A critical heat flux model for saturated flow boiling on the downward curved heated surface. ANN NUCL ENERGY 2018. [DOI: 10.1016/j.anucene.2017.12.038] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Experimental investigation of 3-D ERVC process for IVR strategy – CHF limits and visualization of boiling phenomena. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.06.037] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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Ha KS, Cheung FB, Song J, Park RJ, Kim SB. Prediction of Boiling-Induced Natural-Circulation Flow in Engineered Cooling Channels. NUCL TECHNOL 2017. [DOI: 10.13182/nt13-a15767] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Kwang Soon Ha
- Korea Atomic Energy Research Institute, Daedeok-daero 1045 Yuseong-gu, Daejeon, 305-353, Korea
| | - Fan-Bill Cheung
- The Pennsylvania State University, University Park, Pennsylvania 16802
| | - Jinho Song
- Korea Atomic Energy Research Institute, Daedeok-daero 1045 Yuseong-gu, Daejeon, 305-353, Korea
| | - Rae Joon Park
- Korea Atomic Energy Research Institute, Daedeok-daero 1045 Yuseong-gu, Daejeon, 305-353, Korea
| | - Sang Baik Kim
- Korea Atomic Energy Research Institute, Daedeok-daero 1045 Yuseong-gu, Daejeon, 305-353, Korea
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Rempe J, Farmer M, Corradini M, Ott L, Gauntt R, Powers D. Revisiting Insights from Three Mile Island Unit 2 Postaccident Examinations and Evaluations in View of the Fukushima Daiichi Accident. NUCL SCI ENG 2017. [DOI: 10.13182/nse12-3] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Joy Rempe
- Idaho National Laboratory, Idaho Falls, Idaho
| | | | | | - Larry Ott
- Oak Ridge National Laboratory, Oak Ridge, Tennessee
| | | | - Dana Powers
- Sandia National Laboratories, Albuquerque, New Mexico
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Sartipi A, David R, Petoukhov SM. EXPERIMENTAL STUDY OF STAINLESS STEEL 304L INTERACTION WITH ZIRCALOY AT HIGH TEMPERATURES. CNL NUCLEAR REVIEW 2017. [DOI: 10.12943/cnr.2017.00001] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
Affiliation(s)
- Amirabbas Sartipi
- Canadian Nuclear Laboratories, Chalk River, ON K0J 1J0, Canada
- Canadian Nuclear Laboratories, Chalk River, ON K0J 1J0, Canada
| | - Robert David
- Canadian Nuclear Laboratories, Chalk River, ON K0J 1J0, Canada
- Canadian Nuclear Laboratories, Chalk River, ON K0J 1J0, Canada
| | - Sergei M. Petoukhov
- Canadian Nuclear Laboratories, Chalk River, ON K0J 1J0, Canada
- Canadian Nuclear Laboratories, Chalk River, ON K0J 1J0, Canada
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Narayanan S, Cheung FB, Hochreiter L. Optimal Gap Size for Downward Facing Boiling and Steam Venting in a Hemispherical Annular Channel. NUCL TECHNOL 2017. [DOI: 10.13182/nt09-a8861] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Shankar Narayanan
- The Pennsylvania State University Department of Mechanical and Nuclear, Engineering, 304 Reber Building University Park, Pennsylvania 16802
| | - Fan-Bill Cheung
- The Pennsylvania State University Department of Mechanical and Nuclear, Engineering, 304 Reber Building University Park, Pennsylvania 16802
| | - Lawrence Hochreiter
- The Pennsylvania State University Department of Mechanical and Nuclear, Engineering, 304 Reber Building University Park, Pennsylvania 16802
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Song J, Huh C, Suh N. Improvement of Molten Core Cooling Strategy in a Severe Accident Management Guideline. NUCL TECHNOL 2017. [DOI: 10.13182/nt12-a13592] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Jinho Song
- Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yusong-gu Daejon 305-353, Republic of Korea
| | - Changwook Huh
- Korea Institute of Nuclear Safety, 19 Guseong-dong, Yusong-gu Daejon 305-338, Republic of Korea
| | - Namduk Suh
- Korea Institute of Nuclear Safety, 19 Guseong-dong, Yusong-gu Daejon 305-338, Republic of Korea
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Mori S, Mt Aznam S, Yanagisawa R, Okuyama K. CHF enhancement by honeycomb porous plate in saturated pool boiling of nanofluid. J NUCL SCI TECHNOL 2015. [DOI: 10.1080/00223131.2015.1087353] [Citation(s) in RCA: 15] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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Ma L, Li J, Ji S, Chang H. Turbulent convection experiment at high Rayleigh number to support CAP1400 IVR strategy. NUCLEAR ENGINEERING AND DESIGN 2015. [DOI: 10.1016/j.nucengdes.2015.05.031] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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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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Jung J, An SM, Ha KS, Kim HY. Evaluation of heat-flux distribution at the inner and outer reactor vessel walls under the in-vessel retention through external reactor vessel cooling condition. NUCLEAR ENGINEERING AND TECHNOLOGY 2015. [DOI: 10.1016/j.net.2014.11.005] [Citation(s) in RCA: 14] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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Tusheva P, Altstadt E, Willschütz HG, Fridman E, Weiß FP. Investigations on in-vessel melt retention by external cooling for a generic VVER-1000 reactor. ANN NUCL ENERGY 2015. [DOI: 10.1016/j.anucene.2014.07.044] [Citation(s) in RCA: 17] [Impact Index Per Article: 1.9] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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Flow boiling CHF enhancement in an external reactor vessel cooling (ERVC) channel using graphene oxide nanofluid. NUCLEAR ENGINEERING AND DESIGN 2013. [DOI: 10.1016/j.nucengdes.2013.08.064] [Citation(s) in RCA: 27] [Impact Index Per Article: 2.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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Ozrin V, Tarasov V, Filippov A, Moiseenko E, Tarasov O. Distribution of fission product residual decay heat in stratified core melt of LWR and its influence on sidewall heat flux. NUCLEAR ENGINEERING AND DESIGN 2013. [DOI: 10.1016/j.nucengdes.2013.03.043] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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DEWITT G, MCKRELL T, BUONGIORNO J, HU L, PARK R. EXPERIMENTAL STUDY OF CRITICAL HEAT FLUX WITH ALUMINA-WATER NANOFLUIDS IN DOWNWARD-FACING CHANNELS FOR IN-VESSEL RETENTION APPLICATIONS. NUCLEAR ENGINEERING AND TECHNOLOGY 2013. [DOI: 10.5516/net.02.2012.075] [Citation(s) in RCA: 34] [Impact Index Per Article: 3.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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Park SD, Bang IC. Feasibility of flooding the reactor cavity with liquid gallium coolant for IVR-ERVC strategy. NUCLEAR ENGINEERING AND DESIGN 2013. [DOI: 10.1016/j.nucengdes.2013.01.011] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
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Noh SW, Suh KY. Critical heat flux for APR1400 lower head vessel during a severe accident. NUCLEAR ENGINEERING AND DESIGN 2013. [DOI: 10.1016/j.nucengdes.2012.12.021] [Citation(s) in RCA: 26] [Impact Index Per Article: 2.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Park SD, Lee SW, Kang S, Kim SM, Bang IC. Pool boiling CHF enhancement by graphene-oxide nanofluid under nuclear coolant chemical environments. NUCLEAR ENGINEERING AND DESIGN 2012. [DOI: 10.1016/j.nucengdes.2012.07.016] [Citation(s) in RCA: 42] [Impact Index Per Article: 3.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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Kim TI, Park HM, Chang SH. CHF experiments using a 2-D curved test section with additives for IVR-ERVC strategy. NUCLEAR ENGINEERING AND DESIGN 2012. [DOI: 10.1016/j.nucengdes.2011.11.031] [Citation(s) in RCA: 18] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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Bang IC, Jeong JH. NANOTECHNOLOGY FOR ADVANCED NUCLEAR THERMAL-HYDRAULICS AND SAFETY: BOILING AND CONDENSATION. NUCLEAR ENGINEERING AND TECHNOLOGY 2011. [DOI: 10.5516/net.2011.43.3.217] [Citation(s) in RCA: 44] [Impact Index Per Article: 3.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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Bang IC, Heo GY, Jeong YH, Heo S. AN AXIOMATIC DESIGN APPROACH OF NANOFLUID-ENGINEERED NUCLEAR SAFETY FEATURES FOR GENERATION III+ REACTORS. NUCLEAR ENGINEERING AND TECHNOLOGY 2009. [DOI: 10.5516/net.2009.41.9.1157] [Citation(s) in RCA: 14] [Impact Index Per Article: 0.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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Kang KM, Noh SW, Suh KY. PROPOSAL FOR DUAL PRESSURIZED LIGHT WATER REACTOR UNIT PRODUCING 2000 MWE. NUCLEAR ENGINEERING AND TECHNOLOGY 2009. [DOI: 10.5516/net.2009.41.8.1005] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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Buongiorno J, Hu L, Apostolakis G, Hannink R, Lucas T, Chupin A. A feasibility assessment of the use of nanofluids to enhance the in-vessel retention capability in light-water reactors. NUCLEAR ENGINEERING AND DESIGN 2009. [DOI: 10.1016/j.nucengdes.2008.06.017] [Citation(s) in RCA: 96] [Impact Index Per Article: 6.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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