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Magni MC, Marcel CP, Delmastro DF. Thermal-hydraulic stability investigations of once through helically coiled steam generators for SMR applications. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.111887] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Pilehvar A, Esteki M, Ansarifar G, Hedayat A. Nonlinear stability analysis of a self-pressurized, natural circulation integral reactor via the Lyapunov's second method. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107692] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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Pilehvar A, Esteki M, Ansarifar G, Hedayat A. Stability analysis and parametric study of natural circulation integrated self-pressurized water reactor. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2019.107279] [Citation(s) in RCA: 8] [Impact Index Per Article: 2.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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Zhao Y, Peng M, Xu Y, Xia G, Wang C. Analysis of the transient performance of the flashing-driven natural circulation IPWR. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2019.04.059] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
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Singh S, Singal G, Nayak AK. Numerical Investigation on the Natural Circulation Thermal Hydraulic Characteristics of a Pressure Tube Type Boiling Water Reactor. NUCL SCI ENG 2017. [DOI: 10.1080/00295639.2017.1307048] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
Affiliation(s)
- Sapna Singh
- Homi Bhabha National Institute, Anushakti Nagar, Mumbai 400094, India
| | - Garima Singal
- Bhabha Atomic Research Centre, Reactor Engineering Division, Mumbai 400085, India
| | - A. K. Nayak
- Homi Bhabha National Institute, Anushakti Nagar, Mumbai 400094, India
- Bhabha Atomic Research Centre, Reactor Engineering Division, Mumbai 400085, India
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Marcel C, Furci H, Delmastro D, Masson V. Phenomenology involved in self-pressurized, natural circulation, low thermo-dynamic quality, nuclear reactors: The thermal–hydraulics of the CAREM-25 reactor. NUCLEAR ENGINEERING AND DESIGN 2013. [DOI: 10.1016/j.nucengdes.2012.09.005] [Citation(s) in RCA: 20] [Impact Index Per Article: 1.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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T’Joen C, Rohde M. Experimental study of the coupled thermo-hydraulic–neutronic stability of a natural circulation HPLWR. NUCLEAR ENGINEERING AND DESIGN 2012. [DOI: 10.1016/j.nucengdes.2011.10.055] [Citation(s) in RCA: 29] [Impact Index Per Article: 2.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
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T’Joen C, Gilli L, Rohde M. Sensitivity analysis of numerically determined linear stability boundaries of a supercritical heated channel. NUCLEAR ENGINEERING AND DESIGN 2011. [DOI: 10.1016/j.nucengdes.2011.07.005] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
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