Abstract
This paper presents the outline of core thermohydraulic design and analysis of the research reactor, JRR-3, which is to be upgraded to a 20 MWt pool-type, light water-cooled reactor with 20% LEU plate-type fuels. The major feature of core thermohydraulics of the upgraded JRR-3 is that core flow is a downflow at the condition of normal operation, with which fuel plates are exposed to a severer condition than with an upflow in case of operational transients and accidents. The core thermo-hydraulic design was, therefore, done for the condition of normal operation so that fuel plates may have enough safety margin both against the onset of nucleate boiling not to allow the nucleate boiling anywhere in the core and against the initiation of DNB, and the safety margin for these were evaluated. The core velocity thus designed is at the optimum condition where fuel plates have the maximum margin against the onset of nucleate boiling. The core thermohydraulic characteristics were also clarified for the natural circulation cooling mode. (author)
Sudo, Y;
Ando, H;
Ikawa, H;
Ohnishi, N
[1]
- Department of Research Reactor Operation, Japan Atomic Energy Research Institute (JAERI), 319-11 Tokai-Mura, Ibaraki-Ken (Japan)
Citation Formats
Sudo, Y, Ando, H, Ikawa, H, and Ohnishi, N.
Core thermohydraulic design with LEU fuels for upgraded research reactor, JRR-3.
IAEA: N. p.,
1985.
Web.
Sudo, Y, Ando, H, Ikawa, H, & Ohnishi, N.
Core thermohydraulic design with LEU fuels for upgraded research reactor, JRR-3.
IAEA.
Sudo, Y, Ando, H, Ikawa, H, and Ohnishi, N.
1985.
"Core thermohydraulic design with LEU fuels for upgraded research reactor, JRR-3."
IAEA.
@misc{etde_20571768,
title = {Core thermohydraulic design with LEU fuels for upgraded research reactor, JRR-3}
author = {Sudo, Y, Ando, H, Ikawa, H, and Ohnishi, N}
abstractNote = {This paper presents the outline of core thermohydraulic design and analysis of the research reactor, JRR-3, which is to be upgraded to a 20 MWt pool-type, light water-cooled reactor with 20% LEU plate-type fuels. The major feature of core thermohydraulics of the upgraded JRR-3 is that core flow is a downflow at the condition of normal operation, with which fuel plates are exposed to a severer condition than with an upflow in case of operational transients and accidents. The core thermo-hydraulic design was, therefore, done for the condition of normal operation so that fuel plates may have enough safety margin both against the onset of nucleate boiling not to allow the nucleate boiling anywhere in the core and against the initiation of DNB, and the safety margin for these were evaluated. The core velocity thus designed is at the optimum condition where fuel plates have the maximum margin against the onset of nucleate boiling. The core thermohydraulic characteristics were also clarified for the natural circulation cooling mode. (author)}
place = {IAEA}
year = {1985}
month = {Jul}
}
title = {Core thermohydraulic design with LEU fuels for upgraded research reactor, JRR-3}
author = {Sudo, Y, Ando, H, Ikawa, H, and Ohnishi, N}
abstractNote = {This paper presents the outline of core thermohydraulic design and analysis of the research reactor, JRR-3, which is to be upgraded to a 20 MWt pool-type, light water-cooled reactor with 20% LEU plate-type fuels. The major feature of core thermohydraulics of the upgraded JRR-3 is that core flow is a downflow at the condition of normal operation, with which fuel plates are exposed to a severer condition than with an upflow in case of operational transients and accidents. The core thermo-hydraulic design was, therefore, done for the condition of normal operation so that fuel plates may have enough safety margin both against the onset of nucleate boiling not to allow the nucleate boiling anywhere in the core and against the initiation of DNB, and the safety margin for these were evaluated. The core velocity thus designed is at the optimum condition where fuel plates have the maximum margin against the onset of nucleate boiling. The core thermohydraulic characteristics were also clarified for the natural circulation cooling mode. (author)}
place = {IAEA}
year = {1985}
month = {Jul}
}