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Report No.
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Post irradiation evaluation of high purity stainless steel for high-performance fuel cladding

Ioka, Ikuo ; Ishijima, Yasuhiro ; Kiuchi, Kiyoshi; Kizaki, Minoru; Kato, Yoshiaki; Fujimura, Ken*; Obata, Hiroyuki*

The IASCC and loss of ductility concerning new cladding materials for ultra-high burnup of fuel elements with MOX fuels aiming at 100GWd/t of BWR was performed after neutron irradiation. The specimens machined from tubes made of Fe-25Cr-35Ni-0.2Ti UHP and SUS304 were irradiated at 290$$^{circ}$$C up to 1.8dpa(1.5$$times$$10$$^{25}$$n/m$$^{2}$$) in JRR-3. The ultimate tensile strength of both specimens increased and the fracture elongation decreased in tensile test at 288$$^{circ}$$C. The loss of ductility was almost equal with data of previous literatures. IASCC was recognized on SUS304 by SSRT testing under high temperature water, but not on Fe-25Cr-35Ni-0.2Ti UHP.

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