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For: 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] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]

For:	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] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]

Number

Cited by Other Article(s)

Momotov VN, Erin EA, Tikhonova DE. Dissolution of Spent Nuclear Fuel Samples for Analytical Purposes. RADIOCHEMISTRY 2022. [DOI: 10.1134/s1066362222050010] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 12/16/2022]

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]

Hengra NH, Ilyas M, Mushtaq MH, Inayat MH. Evaluation of the success of in-vessel corium retention using external reactor vessel cooling mechanism for a small PWR. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104286] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]

Influence of crust formation on the heat load to a reactor vessel under an in-vessel retention condition. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2021.108813] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]

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]

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]

An SM, Jung J, Kim HY. Experimental investigations on penetration failure by tube ejection for an APR1400 ICI nozzle during a severe accident. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107810] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]

Shams A, Dovizio D, Zwijsen K, Le Guennic C, Saas L, Le Tellier R, Peybernes M, Bigot B, Skrzypek E, Skrzypek M, Vyskocil L, Carenini L, Fichot F. Status of computational fluid dynamics for in-vessel retention: Challenges and achievements. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2019.107004] [Citation(s) in RCA: 10] [Impact Index Per Article: 2.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]

David R. Calculation of Heat Fluxes Exiting a CANDU Calandria During In-Vessel Retention. NUCL TECHNOL 2019. [DOI: 10.1080/00295450.2019.1597581] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]

Modelling issues related to molten pool behaviour in case of In-Vessel Retention strategy. ANN NUCL ENERGY 2018. [DOI: 10.1016/j.anucene.2018.04.032] [Citation(s) in RCA: 20] [Impact Index Per Article: 3.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/17/2022]

Prasad SV, Nayak A. Investigation of thermo mechanical behaviour in the scaled PHWR stepped calandria vessel during severe accident. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.06.009] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]

The influence of the crust layer on RPV structural failure under severe accident condition. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.02.033] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]

Modeling of Reinforced Concrete for Reactor Cavity Analysis under Energetic Steam Explosion Condition. NUCLEAR ENGINEERING AND TECHNOLOGY 2016. [DOI: 10.1016/j.net.2015.09.009] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]