In the case of sodium- and molten salt–cooled SMRs, the primary coolant will be chemically reactive, heated to temperatures >500 °C, and highly radioactive. Under these extreme conditions, reactor components can have a shorter lifetime than the standard PWR (60 y), and this will increase decommissioning LILW volumes. In addition, nonlight water SMRs will introduce uncommon types of LILW in the form of neutron reflectors and chemically reactive coolant or moderator materials...
Molten salt reactor vessel lifetimes will be limited by the corrosive, high-temperature, and radioactive in-core environment. In particular, the chromium content of 316-type stainless steel that constitutes a PWR pressure vessel is susceptible to corrosion in halide salts. Nevertheless, some developers, such as ThorCon, plan to adopt this stainless steel...
Terrestrial Energy may construct their 400-MWth IMSR vessel from Hastelloy N, a nickel-based alloy that has not been code certified for commercial nuclear applications by the American Society of Mechanical Engineers. Since this nickel-based alloy suffers from helium embrittlement, Terrestrial Energy envisions a 7-y lifetime for their reactor vessel. Molten salt reactor vessels will become contaminated by salt-insoluble fission products and will also become neutron-activated through exposure to a thermal neutron flux greater than 1012 neutrons/cm2-s. Thus, it is unlikely that a commercially viable decontamination process will enable the recycling of their alloy constituents...
Conclusions
This analysis of three distinct SMR designs shows that, relative to a gigawatt-scale PWR, these reactors will increase the energy-equivalent volumes of SNF, long-lived LILW, and short-lived LILW by factors of up to 5.5, 30, and 35, respectively. These findings stand in contrast to the waste reduction benefits that advocates have claimed for advanced nuclear technologies.