Study of Low Activation Materials for Fusion Reactor

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In order to obtain the fundamental data on the development of fusion reactor structural materials, Fe-Cr-Mn austenitic steel, modified 316 Stainless steels, ferritic steels and vanadium alloys were irradiated by neutrons, electrons and/or ions irradiations. Furtheremore the model alloys related these alloys were also irradiated. From these experimentals facts the following results and suggetion were obtained :(1) The modified 316 stainless steel showed lower swelling, and it is expected that these steels are lower radio-activated at lower dose of 30dpa. Therefore, the modified 316 stainless steels could be used as fusion react-or marerials for shorter periods.(2) Phase stability of low activated Fe-Cr-Mn steels was lower at temperature of above 500ﾟC.Therefore, when this type of steels are used for fusion reactor, it is aveirable as buck-up materials of structure components at lower temperature below 200ﾟC.(3) Instead of austenitic steels, the low activated Fe-(9-12)Cr based ferritic steels will be available for DEMO after ITER.However, there is still psome problems to be resolved, that is embrittlement due to helium introduced as a result of transmutation.(4) Future materials for fusion reactor, vanadium alloys are expected, because of the well characteristics of this alloy for radio-activation, the resistance against irradiation and high temperature strength. At present the alloy of V-4Cr-Ti based alloys can be recommended, but these alloys are very sensitive for interstitial impurities such as oxygen and hydrogen. Therefore, if the alloys will be used as first wall materials, the effect of the impurities should be avoided.(5) As the alloy development for long periods, other new matreials such as SiC and intermetallic coumpound will be needed.