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In an accelerator driven system (ADS), the beam window material of spallation neutron target will be heavily irradiated under severe conditions, where the displacement damage and high concentrations of helium and hydrogen atom accumulation in the material will occur simultaneously due to high energy spallation neutron and/or proton irradiations in the lead bismuth flow. A main materials issue dedicated to the ADS is the compatibility with the liquid metal of lead bismuth eutectic (LBE), such as liquid metal embrittlement (LME) and liquid metal corrosion (LMC). In this study, we address firstly the swelling behavior of the beam window materials, which is also important for the fuel claddings and connected indirectly with the oxidation reaction induced during irradiation or/and by the irradiation damage. Secondly, the LMC after ion irradiation of ferritic/martensitic steels, T91, are also addressed in the cases of self-ion irradiation and simultaneous irradiation with He and H atoms. The irradiations were performed at temperatures from 350 to 550°C up to 10 40 dpa. In the case of single ion irradiation (only displacement damage), no cavities were observed, but in the cases of dual and triple ion irradiations, many cavities were formed and caused swelling. It was concluded that helium and/or hydrogen enhanced the swelling induced by the simultaneous irradiation case and the peak swelling behavior appeared at an irradiation temperature around 450°C. It was found that, under simultaneous triple ion beams (Fe+He+H), H atoms affected significantly on the swelling development process. Comparing with the dual beams (Fe+He), the enhancement of cavity growth in the deeper region and the suppression of the growth in the medium depth region with changing the number density distributions of cavities might be caused by a fast diffusion of hydrogen atoms. From this result it can be concluded that the swelling of T91 steel depends on the implantation rates of He/dpa and H/dpa. The initial study was originally performed on LMC of T91 steels using the specimen irradiated at 450°C. After the corrosion test at 450°C in the LBE with low oxygen concentration, the surface of the triply irradiated area was covered by the oxide layer even though the non-irradiated area didn’t show the enough oxide formation. Therefore, it is concluded that the irradiation can enhance the oxide layer formation supposed due to the two reasons of (1) enhancement of Fe diffusion caused by reducing activation energy of Fe atoms due to helium-vacancy complexes and vacancy clusters after the ion irradiation and (2) enhancement of O interstitial diffusion by radiation defects.

Irradiation Influence on Swelling and Corrosion Behavior of ADS Beam Window Materials, T91 Steels, in Lead Bismuth