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For: Bokhari I, Mahmood T. Analysis of loss of flow accident at Pakistan research reactor-1. ANN NUCL ENERGY 2005. [DOI: 10.1016/j.anucene.2005.07.006] [Citation(s) in RCA: 18] [Impact Index Per Article: 0.9] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
Number Cited by Other Article(s)
1
Preliminary study on thermal–hydraulic behavior of loss-of-flow accident in deep pool-type nuclear reactor. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.108992] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
2
Wang G, Wang B, Wen J, Tian R, Niu Z, Liu X. Investigation on the hydraulic process of inertia tank in the case of pump trips. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111195] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
3
Almachi JC, Sánchez-Espinoza V, Imke U. Extension and validation of the SubChanFlow code for the thermo-hydraulic analysis of MTR cores with plate-type fuel assemblies. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111221] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
4
Al-Yahia OS, Lee H, Jo D. Transient analyses of the Jordanian 5 MW research reactor under LOEP accident. ANN NUCL ENERGY 2016. [DOI: 10.1016/j.anucene.2015.10.021] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
5
Davari A, Mirvakili SM, Abedi E. Three-dimensional analysis of flow blockage accident in Tehran MTR research reactor core using CFD. PROGRESS IN NUCLEAR ENERGY 2015. [DOI: 10.1016/j.pnucene.2015.08.008] [Citation(s) in RCA: 11] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
6
Pappas C, Ikonomopoulos A, Sfetsos A, Andronopoulos S, Varvayanni M, Catsaros N. Derivation of the source term, dose results and associated radiological consequences for the Greek Research Reactor – 1. NUCLEAR ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.nucengdes.2014.04.008] [Citation(s) in RCA: 12] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
7
Ramajo D, Corzo S, Schiliuk N, Nigro N. 3D modeling of the primary circuit in the reactor pressure vessel of a PHWR. NUCLEAR ENGINEERING AND DESIGN 2013. [DOI: 10.1016/j.nucengdes.2013.06.031] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
8
El-Morshedy SED. Prediction, analysis and solution of flow inversion phenomenon in a typical MTR reactor with upward core cooling. KERNTECHNIK 2013. [DOI: 10.3139/124.110110] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
9
Modeling and simulation of loss of the ultimate heat sink in a typical material testing reactor. ANN NUCL ENERGY 2013. [DOI: 10.1016/j.anucene.2012.07.031] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
10
El-Morshedy SED. Thermal-hydraulic modeling and analysis of a tank in pool reactor for normal operation and loss of flow transient. PROGRESS IN NUCLEAR ENERGY 2012. [DOI: 10.1016/j.pnucene.2012.07.005] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
11
Awan SE, Mirza NM, Mirza SM. Kinetic study of fission product activity released inside containment under loss of coolant transients in a typical MTR system. Appl Radiat Isot 2012;70:2711-9. [PMID: 23041390 DOI: 10.1016/j.apradiso.2012.08.002] [Citation(s) in RCA: 9] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 05/15/2012] [Revised: 07/25/2012] [Accepted: 08/07/2012] [Indexed: 10/28/2022]
12
Salama A. CFD analysis of fast loss of flow accident in typical MTR reactor undergoing partial and full blockage: The average channel scenario. PROGRESS IN NUCLEAR ENERGY 2012. [DOI: 10.1016/j.pnucene.2012.05.002] [Citation(s) in RCA: 19] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
13
Salama A, El-Morshedy SED. CFD simulation of flow blockage through a coolant channel of a typical material testing reactor core. ANN NUCL ENERGY 2012. [DOI: 10.1016/j.anucene.2011.09.005] [Citation(s) in RCA: 33] [Impact Index Per Article: 2.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
14
Salama A, El-Morshedy SED. CFD analysis of flow blockage in MTR coolant channel under loss-of-flow transient: Hot channel scenario. PROGRESS IN NUCLEAR ENERGY 2012. [DOI: 10.1016/j.pnucene.2011.11.005] [Citation(s) in RCA: 22] [Impact Index Per Article: 1.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
15
El-Morshedy SED. Prediction, analysis and solution of the flow inversion phenomenon in a typical MTR-reactor with upward core cooling. NUCLEAR ENGINEERING AND DESIGN 2011. [DOI: 10.1016/j.nucengdes.2010.10.006] [Citation(s) in RCA: 8] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
16
Lu Q, Qiu S, Su G. Development of a thermal–hydraulic analysis code for research reactors with plate fuels. ANN NUCL ENERGY 2009. [DOI: 10.1016/j.anucene.2008.11.038] [Citation(s) in RCA: 19] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
17
Lu Q, Qiu S, Su G. Flow blockage analysis of a channel in a typical material test reactor core. NUCLEAR ENGINEERING AND DESIGN 2009. [DOI: 10.1016/j.nucengdes.2008.06.016] [Citation(s) in RCA: 42] [Impact Index Per Article: 2.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
18
Engineered safety feature, an emergency core cooling system at Pakistan research reactor-1. ANN NUCL ENERGY 2008. [DOI: 10.1016/j.anucene.2007.11.005] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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