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An investigation for the fuel temperature of the Tehran research reactor during a complete loss of coolant accident. PROGRESS IN NUCLEAR ENERGY 2020. [DOI: 10.1016/j.pnucene.2020.103489] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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Ribeiro ER, Palma DA, Henrice Jr E, Su J. Transient analysis of the Brazilian Multipurpose Reactor by the coupled neutronics and thermal hydraulics code NTHC1. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107449] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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Hedayat A. Simulation and analysis of the Loss of Flow Accident (LOFA) scenarios for an open pool type research reactor by using the RELAP5/MOD3.2 code. KERNTECHNIK 2019. [DOI: 10.3139/124.110943] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
Abstract
AbstractIn this paper, a 5 MW open pool type research reactor is simulated and analyzed to check and pass a complete and practical safety assessment against various LOFA scenarios. Generally, LOFA may occur in a research reactor when the reactor primary pump or the safety flapper valve fail. The simulation includes the study of a downward core cooling system circulated by the gravity driven force, the performance and failure effects of the safety flapper valve, the flow reversal mode and transition, the natural convection mode, different possible types of LOFA, and impacts of the surrounding empty boxes. First of all, the code nodalization is successfully benchmarked against available experimental data of the reactor operating parameters. Then, all possible DBAs in this field of study are simulated and discussed in detail. Results are completely satisfactory to simulate and analyze a pool-type research reactor in response to LOFA using the RELAP5 code. Furthermore, transients including the natural convection mode and even flow reversal mode are following naturally without any oscillation or source of errors. Finally, TRR is completely safe against the DBA type of LOFA scenarios.
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Affiliation(s)
- A. Hedayat
- 1Reactor and nuclear safety school Nuclear Science and Technology Research Institute (NSTRI) End of North Karegar Street P. O. Box 14395-836, Tehran Iran
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Hedayat A. Simulation and transient analyses of a complete passive heat removal system in a downward cooling pool-type material testing reactor against a complete station blackout and long-term natural convection mode using the RELAP5/3.2 code. NUCLEAR ENGINEERING AND TECHNOLOGY 2017. [DOI: 10.1016/j.net.2017.03.009] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
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Savva P, Chatzidakis S, Varvayanni M, Ikonomopoulos A, Chrysanthopoulou N, Catsaros N, Antonopoulos-Domis M. Optimized Flux Trap Dimensions in a Research Reactor Core. NUCL TECHNOL 2017. [DOI: 10.13182/nt13-108] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- P. Savva
- National Centre for Scientific Research “Demokritos,” Institute of Nuclear & Radiological Sciences & Technology, Energy & Safety, Nuclear Research Reactor Laboratory, 15310 Aghia Paraskevi, Athens, Greece
| | - S. Chatzidakis
- Purdue University, School of Nuclear Engineering, West Lafayette, Indiana 47907
| | - M. Varvayanni
- National Centre for Scientific Research “Demokritos,” Institute of Nuclear & Radiological Sciences & Technology, Energy & Safety, Nuclear Research Reactor Laboratory, 15310 Aghia Paraskevi, Athens, Greece
| | - A. Ikonomopoulos
- National Centre for Scientific Research “Demokritos,” Institute of Nuclear & Radiological Sciences & Technology, Energy & Safety, Nuclear Research Reactor Laboratory, 15310 Aghia Paraskevi, Athens, Greece
| | - N. Chrysanthopoulou
- National Centre for Scientific Research “Demokritos,” Institute of Nuclear & Radiological Sciences & Technology, Energy & Safety, Nuclear Research Reactor Laboratory, 15310 Aghia Paraskevi, Athens, Greece
- National Technical University of Athens, School of Applied Mathematical and Physical Sciences Department of Physics, Athens, Greece
| | - N. Catsaros
- National Centre for Scientific Research “Demokritos,” Institute of Nuclear & Radiological Sciences & Technology, Energy & Safety, Nuclear Research Reactor Laboratory, 15310 Aghia Paraskevi, Athens, Greece
| | - M. Antonopoulos-Domis
- Aristotle University of Thessaloniki, School of Electrical and Computer Engineering Nuclear Engineering Laboratory, Thessaloniki, Greece
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Natural convection cooling characteristics in a plate type fuel assembly of Kyoto University Research Reactor during loss of coolant accident. ANN NUCL ENERGY 2016. [DOI: 10.1016/j.anucene.2015.11.035] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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Park K, Khor CL. Consideration on hydrogen explosion scenario in APR 1400 containment building during small breakup loss of coolant accident. NUCLEAR ENGINEERING AND DESIGN 2015. [DOI: 10.1016/j.nucengdes.2015.07.041] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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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: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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