Study on Detailed Calculation and Experiment Methods of Neutronics, Fuel Materials, and Thermal Hydraulics for a Commercial Type Japanese Sodium-Cooled Fast Reactor

<table>Schematic of JSFR-1500, showing the 2-loop arrangement with straight-tube heat exchangers, and with the primary pumps integrated into the Intermediate Heat Exchanger (IHX) (reproduced from [<a href="/journals/stni/2012/351809/#B7">7</a>]).</table>

Science and Technology of Nuclear Installations

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Figure 1

Figure 1: Study on Detailed Calculation and Experiment Methods of Neutronics, Fuel Materials, and Thermal Hydraulics for a Commercial Type Japanese Sodium-Cooled Fast Reactor 

Figure 1 | Study on Detailed Calculation and Experiment Methods of Neutronics, Fuel Materials, and Thermal Hydraulics for a Commercial Type Japanese Sodium-Cooled Fast Reactor 