Abstract
The Multiple Purpose Research Reactor MEX-15 is a 15 MW thermal power, swimming pool type research reactor and will be constructed by the National Institute of Nuclear Research (ININ) of Mexico. Demineralized light water will be used as coolant and moderator. The reactor core will be surrounding by graphite reflectors. The reactor will use 19.75% enriched U{sub 3}O{sub 8}-A1 plate-type fuel (MTR-type). The core thermal-hydraulic conceptual design of the MEX-15 was performed for two cooling modes, forced convection cooling and natural convection cooling. The key criteria are first to avoid the nucleate boiling anywhere in the core and second to have enough safety margin to the DNB for normal operation conditions. The results of the thermalhydraulic conceptual design and analysis show that the optimum coolant velocity in the standard fuel element is about 5.6 m/s with the minimum temperature margin against the ONB temperature of about 17degC and the minimum DNBR of 2.58 for the forced-convection cooling mode at a core power of 15 MW with the pressures of 1.43 kg/cm{sup 2} at the core inlet and a core inlet coolant temperature of 35degC. It was also determined that the total core power up to about 300 kW can be
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Lucatero, M A;
[1]
Kaminaga, Masanori
- Instituto Nacional de Investigaciones Nucleares Mexico City (Mexico)
Citation Formats
Lucatero, M A, and Kaminaga, Masanori.
Thermal-hydraulic conceptual design of the multiple purpose research reactor.
Japan: N. p.,
1994.
Web.
Lucatero, M A, & Kaminaga, Masanori.
Thermal-hydraulic conceptual design of the multiple purpose research reactor.
Japan.
Lucatero, M A, and Kaminaga, Masanori.
1994.
"Thermal-hydraulic conceptual design of the multiple purpose research reactor."
Japan.
@misc{etde_10156024,
title = {Thermal-hydraulic conceptual design of the multiple purpose research reactor}
author = {Lucatero, M A, and Kaminaga, Masanori}
abstractNote = {The Multiple Purpose Research Reactor MEX-15 is a 15 MW thermal power, swimming pool type research reactor and will be constructed by the National Institute of Nuclear Research (ININ) of Mexico. Demineralized light water will be used as coolant and moderator. The reactor core will be surrounding by graphite reflectors. The reactor will use 19.75% enriched U{sub 3}O{sub 8}-A1 plate-type fuel (MTR-type). The core thermal-hydraulic conceptual design of the MEX-15 was performed for two cooling modes, forced convection cooling and natural convection cooling. The key criteria are first to avoid the nucleate boiling anywhere in the core and second to have enough safety margin to the DNB for normal operation conditions. The results of the thermalhydraulic conceptual design and analysis show that the optimum coolant velocity in the standard fuel element is about 5.6 m/s with the minimum temperature margin against the ONB temperature of about 17degC and the minimum DNBR of 2.58 for the forced-convection cooling mode at a core power of 15 MW with the pressures of 1.43 kg/cm{sup 2} at the core inlet and a core inlet coolant temperature of 35degC. It was also determined that the total core power up to about 300 kW can be removed by the natural convection cooling under the condition that nucleate boiling is not allowed anywhere in the core. The minimum temperature margin against ONB temperature and the minimum DNBR at 300 kW are 1.6degC and 6.31, respectively. The results obtained in this work establishes the preliminary technical specifications for the core thermal-hydraulic design of the Multiple Purpose Research Reactor MEX-15. (author).}
place = {Japan}
year = {1994}
month = {Feb}
}
title = {Thermal-hydraulic conceptual design of the multiple purpose research reactor}
author = {Lucatero, M A, and Kaminaga, Masanori}
abstractNote = {The Multiple Purpose Research Reactor MEX-15 is a 15 MW thermal power, swimming pool type research reactor and will be constructed by the National Institute of Nuclear Research (ININ) of Mexico. Demineralized light water will be used as coolant and moderator. The reactor core will be surrounding by graphite reflectors. The reactor will use 19.75% enriched U{sub 3}O{sub 8}-A1 plate-type fuel (MTR-type). The core thermal-hydraulic conceptual design of the MEX-15 was performed for two cooling modes, forced convection cooling and natural convection cooling. The key criteria are first to avoid the nucleate boiling anywhere in the core and second to have enough safety margin to the DNB for normal operation conditions. The results of the thermalhydraulic conceptual design and analysis show that the optimum coolant velocity in the standard fuel element is about 5.6 m/s with the minimum temperature margin against the ONB temperature of about 17degC and the minimum DNBR of 2.58 for the forced-convection cooling mode at a core power of 15 MW with the pressures of 1.43 kg/cm{sup 2} at the core inlet and a core inlet coolant temperature of 35degC. It was also determined that the total core power up to about 300 kW can be removed by the natural convection cooling under the condition that nucleate boiling is not allowed anywhere in the core. The minimum temperature margin against ONB temperature and the minimum DNBR at 300 kW are 1.6degC and 6.31, respectively. The results obtained in this work establishes the preliminary technical specifications for the core thermal-hydraulic design of the Multiple Purpose Research Reactor MEX-15. (author).}
place = {Japan}
year = {1994}
month = {Feb}
}