Abstract
In order to increase the amount of 235U in the target chamber for KUR-ISOL, the thicknesses of the 235U target and its protective Al covering were reexamined and optimized by calculating the ranges of typical fission products in the target chamber with a SRIM code. It was found that the 235U target could be thickened by up to 6 times of the present target for heavy fission products. Our future plan of relocating the target chamber to another irradiation port at KUR is also described.
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