Abstract
In PWR a 17x17 type fuel assembly is also used in place of the 15x15 type one. In order to evaluate the applicability of the results from 15x15 type simulated fuel assemblies to an actual reactor analysis, it is necessary to make clear the effect of the fuel assembly configuration and the fuel rod configuration. In this study, experiments using small scale reflood test facility were carried out by changing the rod bundle configuration, the grid spacer type and the fuel rod configuration systematically. The effect of each parameter on the core thermal-hydraulics was examined by comparing the experimental data and by using analytical results with REFLA/TRAC code which is applicable to the 15x15 type fuel assembly. The following conclusions were derived from this study: (1) As for the rod bundle configuration, the heat transfer and the void fraction models in REFLA/TRAC can predict the thermal-hydraulics in the 17x17 type fuel assembly within the same error band as for the 15x15 type one. (2) As for the grid spacer type, no significant effects are recognized for the peak clad temperature. The heat transfer and the void fraction models in REFLA/TRAC are applicable regardless of the grid spacer type. Although quench
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Ohnuki, Akira;
Akimoto, Hajime;
Iguchi, Tadashi;
Murao, Yoshio
[1]
- Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Citation Formats
Ohnuki, Akira, Akimoto, Hajime, Iguchi, Tadashi, and Murao, Yoshio.
Effect of fuel assembly configuration and fuel rod configuration on thermal-hydraulic behavior in core during reflood phase of PWR-LOCA.
Japan: N. p.,
1994.
Web.
Ohnuki, Akira, Akimoto, Hajime, Iguchi, Tadashi, & Murao, Yoshio.
Effect of fuel assembly configuration and fuel rod configuration on thermal-hydraulic behavior in core during reflood phase of PWR-LOCA.
Japan.
Ohnuki, Akira, Akimoto, Hajime, Iguchi, Tadashi, and Murao, Yoshio.
1994.
"Effect of fuel assembly configuration and fuel rod configuration on thermal-hydraulic behavior in core during reflood phase of PWR-LOCA."
Japan.
@misc{etde_10102947,
title = {Effect of fuel assembly configuration and fuel rod configuration on thermal-hydraulic behavior in core during reflood phase of PWR-LOCA}
author = {Ohnuki, Akira, Akimoto, Hajime, Iguchi, Tadashi, and Murao, Yoshio}
abstractNote = {In PWR a 17x17 type fuel assembly is also used in place of the 15x15 type one. In order to evaluate the applicability of the results from 15x15 type simulated fuel assemblies to an actual reactor analysis, it is necessary to make clear the effect of the fuel assembly configuration and the fuel rod configuration. In this study, experiments using small scale reflood test facility were carried out by changing the rod bundle configuration, the grid spacer type and the fuel rod configuration systematically. The effect of each parameter on the core thermal-hydraulics was examined by comparing the experimental data and by using analytical results with REFLA/TRAC code which is applicable to the 15x15 type fuel assembly. The following conclusions were derived from this study: (1) As for the rod bundle configuration, the heat transfer and the void fraction models in REFLA/TRAC can predict the thermal-hydraulics in the 17x17 type fuel assembly within the same error band as for the 15x15 type one. (2) As for the grid spacer type, no significant effects are recognized for the peak clad temperature. The heat transfer and the void fraction models in REFLA/TRAC are applicable regardless of the grid spacer type. Although quench velocity model slightly overestimates the quench velocity in the case of grid spacer type of 17x17 type fuel assembly under a low flooding velocity, the difference of the quench velocity between the grid spacer types does not affect the peak clad temperature and the core thermal-hydraulics can be predicted by REFLA/TRAC with good accuracy regardless of the grid spacer type. (3) As for the fuel rod configuration, the effect of the gap is small and the cladding material has a dominant effect. The REFLA/TRAC code is almost able to predict the effect of difference of the fuel rod configuration. From these conclusions, we consider that the results from the 15x15 type simulated fuel assemblies can apply to the evaluation of safety analyses for actual PWRs.}
place = {Japan}
year = {1994}
month = {Aug}
}
title = {Effect of fuel assembly configuration and fuel rod configuration on thermal-hydraulic behavior in core during reflood phase of PWR-LOCA}
author = {Ohnuki, Akira, Akimoto, Hajime, Iguchi, Tadashi, and Murao, Yoshio}
abstractNote = {In PWR a 17x17 type fuel assembly is also used in place of the 15x15 type one. In order to evaluate the applicability of the results from 15x15 type simulated fuel assemblies to an actual reactor analysis, it is necessary to make clear the effect of the fuel assembly configuration and the fuel rod configuration. In this study, experiments using small scale reflood test facility were carried out by changing the rod bundle configuration, the grid spacer type and the fuel rod configuration systematically. The effect of each parameter on the core thermal-hydraulics was examined by comparing the experimental data and by using analytical results with REFLA/TRAC code which is applicable to the 15x15 type fuel assembly. The following conclusions were derived from this study: (1) As for the rod bundle configuration, the heat transfer and the void fraction models in REFLA/TRAC can predict the thermal-hydraulics in the 17x17 type fuel assembly within the same error band as for the 15x15 type one. (2) As for the grid spacer type, no significant effects are recognized for the peak clad temperature. The heat transfer and the void fraction models in REFLA/TRAC are applicable regardless of the grid spacer type. Although quench velocity model slightly overestimates the quench velocity in the case of grid spacer type of 17x17 type fuel assembly under a low flooding velocity, the difference of the quench velocity between the grid spacer types does not affect the peak clad temperature and the core thermal-hydraulics can be predicted by REFLA/TRAC with good accuracy regardless of the grid spacer type. (3) As for the fuel rod configuration, the effect of the gap is small and the cladding material has a dominant effect. The REFLA/TRAC code is almost able to predict the effect of difference of the fuel rod configuration. From these conclusions, we consider that the results from the 15x15 type simulated fuel assemblies can apply to the evaluation of safety analyses for actual PWRs.}
place = {Japan}
year = {1994}
month = {Aug}
}