Abstract
In our earlier paper the target optimization of an electron–neutron (e–n) converter based molten salt ADS concept (MSENC) was presented. In this paper the burnup in this molten salt ADS is investigated. The system is continuously fueled with TRUs obtained from spent nuclear fuel by means of pyrochemical separation, while fission products are continuously filtered out. Effect of MSENC operation on transuranium consumption, mass reduction and radiotoxicity is considered. It seems that while the amount of plutonium is reduced significantly, the higher actinides will build up, which results that radiotoxicity of nuclear waste will not be reduced considerably.
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