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For: Rempe JL, Suh KY, Cheung FB, Kim SB. In-Vessel Retention of Molten Corium: Lessons Learned and Outstanding Issues. NUCL TECHNOL 2017. [DOI: 10.13182/nt08-a3924] [Citation(s) in RCA: 56] [Impact Index Per Article: 8.0] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Number Cited by Other Article(s)
1
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
2
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]
3
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]
4
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]
5
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]
6
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]
7
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]
8
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]
9
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]
10
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]
11
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]
12
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]
13
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]
14
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]
15
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]
16
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]
17
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]
18
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]
19
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]
20
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]
21
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]
22
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]
23
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]
24
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]
25
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]
26
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]
27
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]
28
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]
29
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]
30
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]
31
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]
32
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]
33
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]
34
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]
35
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]
36
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]
37
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]
38
Song J, Suh N. An evolution of molten core cooling strategies. NUCLEAR ENGINEERING AND DESIGN 2009. [DOI: 10.1016/j.nucengdes.2009.02.010] [Citation(s) in RCA: 15] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
39
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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