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Report No.
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Shielding calculation of the radiation condition for the surveillance testing

not registered; Takagi, Shunji*

The neutron flux, reaction rate, gamma flux, and gamma were evaluated by using the radiation shielding calculation code for the estimation of the radiation condition for the surveillance testing heating of JOYO reactor core. Neutron reaction cross sections were calculated from the JENDL dosimetry files. The spatial distributions of neutron and gamma flux were evaluated by using two models. One was the RZ model for the axial and radial distribution, and the other was the XY-R$$theta$$ model for the radial and azimuthal distribution. The collapsed effect of the grouped cross section was estimated by the calculation with the RZ model. The effect of the rack fuel was estimated by the calculation with the XY-R$$theta$$ model.

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