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

<table>U-238 Capture Rate Distribution in a JSFR fuel assembly. Fuel assemblies are grouped into three groups to take into account the influence of the wrapper tube and sodium channels on the self-shielding.</table>

Science and Technology of Nuclear Installations

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Figure 9

Figure 9: Study on Detailed Calculation and Experiment Methods of Neutronics, Fuel Materials, and Thermal Hydraulics for a Commercial Type Japanese Sodium-Cooled Fast Reactor 

Figure 9 | Study on Detailed Calculation and Experiment Methods of Neutronics, Fuel Materials, and Thermal Hydraulics for a Commercial Type Japanese Sodium-Cooled Fast Reactor 