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For: Sehgal B, Theerthan A, Giri A, Karbojian A, Willschütz H, Kymäläinen O, Vandroux S, Bonnet J, Seiler J, Ikkonen K, Sairanen R, Bhandari S, Bürger M, Buck M, Widmann W, Dienstbier J, Techy Z, Kostka P, Taubner R, Theofanous T, Dinh T. Assessment of reactor vessel integrity (ARVI). Nuclear Engineering and Design 2003. [DOI: 10.1016/s0029-5493(02)00343-6] [Citation(s) in RCA: 32] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
Number Cited by Other Article(s)
1
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]
2
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]
3
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]
4
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]
5
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]
6
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]
7
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]
8
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]
9
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]
10
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]
11
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]
12
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]
13
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]
14
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]
15
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]
16
Gu Z. History review of nuclear reactor safety. ANN NUCL ENERGY 2018. [DOI: 10.1016/j.anucene.2018.06.023] [Citation(s) in RCA: 24] [Impact Index Per Article: 4.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
17
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]
18
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]
19
Evaluation of an IVR-ERVC strategy for a high power reactor using MELCOR 2.1. ANN NUCL ENERGY 2017. [DOI: 10.1016/j.anucene.2017.05.045] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
20
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]
21
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]
22
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]
23
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]
24
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]
25
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]
26
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]
27
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]
28
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]
29
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]
30
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]
31
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]
32
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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