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The new multipurpose research reactor is a 30 MW thermal power, swimming pool type research reactor and will be constructed instead of JRR-3 for utilization of the neutron beam, irradiation, training and so on. The core thermal-hydraulic conceptual design of the new multipurpose reactor was performed for the forced convection cooling modes. The key criteria are first to avoid the nucleate boiling anywhere in the core and second to have enough safety margin to departure from nucleate boiling for normal operation conditions. As the results of the thermal-hydraulic analysis, the optimum coolant velocity in the standard fuel element and the core inlet pressure were obtained.

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Steady-state thermal hydraulic analysis and flow channel blockage accident analysis of JRR-3 silicide core

Steady-state thermal hydraulic analysis and flow channel blockage accident analysis of JRR-4 silicide LEU core

COOLOD-N: A Copmupter code, for the analysis of steady-state thermal hydraulics in plate-type research reactor

COOLOD-N2: A Computer code, for the analyses of steady-state thermal-hydraulics in research reactors

Safety analysis of JMTR LEU fuel cores, 2; Thermohydraulic analysis

Thermohydrodynamic characteristic analysis on the steady state condition of JMTR LEU fuel core

COOLOD-N; A Computer code for the analyses of steady-state thermal-hydraulics in plate-type research reactors

Thermohydraulic Characteristics Analysis of Natural Convective Cooling Mode on the Steady State Condition of Upgraded JRR-3 Core,Using COOLOD-N

Thermohydrodynamic Characteristic Analysis on the Steady State Condition of JRR-3 Core(Analysis by COOLOD Code)

Thermal-hydraulic conceptual design of the new multipurpose research reactor succeeding to JRR-3