The Experts below are selected from a list of 204 Experts worldwide ranked by ideXlab platform
Jalil Jafari - One of the best experts on this subject based on the ideXlab platform.
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Loss of Coolant accident analyses on tehran research reactor by relap5 mod3 2 code
Progress in Nuclear Energy, 2007Co-Authors: Afshin Hedayat, H Davilu, Jalil JafariAbstract:In this paper, a Loss of Coolant accident (LOCA) in Tehran research reactor (TRR) is analyzed. The following procedure consists of three major parts. First, a RELAP5 nodalization of the core and the most important components of the primarily cooling system are developed and steady state condition is simulated and compared with experimental data [SAR for TRR, October 2002. Safety analysis report for Tehran research reactor. Nuclear Research Center of the Atomic Energy Organization of Iran, Tehran] to validate the nodalization. Then, two large break points are selected for design basis accident analyses. Finally, two main Loss of Coolant accidents are simulated and developed to analyze LOCA in TRR. It can be concluded that TRR is safe against the LOCA. And also RELAP5/MOD3.2 code can simulate research reactors at operating conditions well but it seems that this code cannot simulates large transient phases of the research reactors accurately as steady state condition specially in low pressure two phase mixtures (water and air).
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Loss of Coolant accident analyses on Tehran research reactor by RELAP5/MOD3.2 code
Progress in Nuclear Energy, 2007Co-Authors: Afshin Hedayat, H Davilu, Jalil JafariAbstract:In this paper, a Loss of Coolant accident (LOCA) in Tehran research reactor (TRR) is analyzed. The following procedure consists of three major parts. First, a RELAP5 nodalization of the core and the most important components of the primarily cooling system are developed and steady state condition is simulated and compared with experimental data [SAR for TRR, October 2002. Safety analysis report for Tehran research reactor. Nuclear Research Center of the Atomic Energy Organization of Iran, Tehran] to validate the nodalization. Then, two large break points are selected for design basis accident analyses. Finally, two main Loss of Coolant accidents are simulated and developed to analyze LOCA in TRR. It can be concluded that TRR is safe against the LOCA. And also RELAP5/MOD3.2 code can simulate research reactors at operating conditions well but it seems that this code cannot simulates large transient phases of the research reactors accurately as steady state condition specially in low pressure two phase mixtures (water and air).
Afshin Hedayat - One of the best experts on this subject based on the ideXlab platform.
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Loss of Coolant accident analyses on tehran research reactor by relap5 mod3 2 code
Progress in Nuclear Energy, 2007Co-Authors: Afshin Hedayat, H Davilu, Jalil JafariAbstract:In this paper, a Loss of Coolant accident (LOCA) in Tehran research reactor (TRR) is analyzed. The following procedure consists of three major parts. First, a RELAP5 nodalization of the core and the most important components of the primarily cooling system are developed and steady state condition is simulated and compared with experimental data [SAR for TRR, October 2002. Safety analysis report for Tehran research reactor. Nuclear Research Center of the Atomic Energy Organization of Iran, Tehran] to validate the nodalization. Then, two large break points are selected for design basis accident analyses. Finally, two main Loss of Coolant accidents are simulated and developed to analyze LOCA in TRR. It can be concluded that TRR is safe against the LOCA. And also RELAP5/MOD3.2 code can simulate research reactors at operating conditions well but it seems that this code cannot simulates large transient phases of the research reactors accurately as steady state condition specially in low pressure two phase mixtures (water and air).
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Loss of Coolant accident analyses on Tehran research reactor by RELAP5/MOD3.2 code
Progress in Nuclear Energy, 2007Co-Authors: Afshin Hedayat, H Davilu, Jalil JafariAbstract:In this paper, a Loss of Coolant accident (LOCA) in Tehran research reactor (TRR) is analyzed. The following procedure consists of three major parts. First, a RELAP5 nodalization of the core and the most important components of the primarily cooling system are developed and steady state condition is simulated and compared with experimental data [SAR for TRR, October 2002. Safety analysis report for Tehran research reactor. Nuclear Research Center of the Atomic Energy Organization of Iran, Tehran] to validate the nodalization. Then, two large break points are selected for design basis accident analyses. Finally, two main Loss of Coolant accidents are simulated and developed to analyze LOCA in TRR. It can be concluded that TRR is safe against the LOCA. And also RELAP5/MOD3.2 code can simulate research reactors at operating conditions well but it seems that this code cannot simulates large transient phases of the research reactors accurately as steady state condition specially in low pressure two phase mixtures (water and air).
H Davilu - One of the best experts on this subject based on the ideXlab platform.
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Loss of Coolant accident analyses on tehran research reactor by relap5 mod3 2 code
Progress in Nuclear Energy, 2007Co-Authors: Afshin Hedayat, H Davilu, Jalil JafariAbstract:In this paper, a Loss of Coolant accident (LOCA) in Tehran research reactor (TRR) is analyzed. The following procedure consists of three major parts. First, a RELAP5 nodalization of the core and the most important components of the primarily cooling system are developed and steady state condition is simulated and compared with experimental data [SAR for TRR, October 2002. Safety analysis report for Tehran research reactor. Nuclear Research Center of the Atomic Energy Organization of Iran, Tehran] to validate the nodalization. Then, two large break points are selected for design basis accident analyses. Finally, two main Loss of Coolant accidents are simulated and developed to analyze LOCA in TRR. It can be concluded that TRR is safe against the LOCA. And also RELAP5/MOD3.2 code can simulate research reactors at operating conditions well but it seems that this code cannot simulates large transient phases of the research reactors accurately as steady state condition specially in low pressure two phase mixtures (water and air).
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Loss of Coolant accident analyses on Tehran research reactor by RELAP5/MOD3.2 code
Progress in Nuclear Energy, 2007Co-Authors: Afshin Hedayat, H Davilu, Jalil JafariAbstract:In this paper, a Loss of Coolant accident (LOCA) in Tehran research reactor (TRR) is analyzed. The following procedure consists of three major parts. First, a RELAP5 nodalization of the core and the most important components of the primarily cooling system are developed and steady state condition is simulated and compared with experimental data [SAR for TRR, October 2002. Safety analysis report for Tehran research reactor. Nuclear Research Center of the Atomic Energy Organization of Iran, Tehran] to validate the nodalization. Then, two large break points are selected for design basis accident analyses. Finally, two main Loss of Coolant accidents are simulated and developed to analyze LOCA in TRR. It can be concluded that TRR is safe against the LOCA. And also RELAP5/MOD3.2 code can simulate research reactors at operating conditions well but it seems that this code cannot simulates large transient phases of the research reactors accurately as steady state condition specially in low pressure two phase mixtures (water and air).
M.h. Esteki - One of the best experts on this subject based on the ideXlab platform.
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Loss of Coolant accident analyses on multi purpose research reactor by RELAP5/MOD3.2 code
Progress in Nuclear Energy, 2015Co-Authors: Masoumeh Karimpour, M.h. EstekiAbstract:In this paper, a Loss of Coolant accident (LOCA) in multi purpose research reactor (MPRR) is analyzed. The following procedure consists of three major parts. First, a RELAP5 nodalization of the core and the most important components of the primarily cooling system are developed and steady state condition is simulated and compared with result of simulation a same Indian research reactor to verify the nodalization. Then, two large break points are selected for design basis accident analyses. Finally, two main Loss of Coolant accidents are simulated and developed to analyze LOCA in MPRR. It can be concluded that MPRR is safe against the LOCA.
Masuro Ogawa - One of the best experts on this subject based on the ideXlab platform.
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thermal analysis of heated cylinder simulating nuclear reactor during Loss of Coolant accident
Journal of Nuclear Science and Technology, 2014Co-Authors: Hiroyuki Sato, Hirofumi Ohashi, Yukio Tachibana, Kazuhiko Kunitomi, Masuro OgawaAbstract:Transient analyses of temperature behavior of reactor during complete Loss-of-Coolant conditions throughout the entire period of accident with scram are presented. The influence of reactor thermal properties, operating power density, geometry of active core and selection of fuel type on the capability of decay heat removal against the accident are studied. It is shown that the reactor design envelope against Loss-of-Coolant accidents is fully determined by the key parameters: operating power density, volumetric heat capacity and thermal conductivity. The range of the envelope is shown to enlarge considerably by selecting high refractory fuel. Above 10% of operating power density in the current nuclear power plants, decay heat removal is not feasible without the presence of Coolant in the reactor. The results suggest sufficient amount of solid materials, made of high-thermal conductance materials such as SiC and graphite, are required inside the reactor to achieve successful decay heat removal in Loss-of-c...
