TBR comparison of water-cooled blanket based on PWR and SCWR water conditions

Nuclear analysis results were compared for water-cooled blanket based on PWR (pressurized water reactor) and SCWR (sub-critical water reactor) water conditions. The local TBR (tritium breeding ratio) in outboard zone was discussed in the range of Pn (neutron wall load) from 1 MW/m2 to 5 MW/m2. It was found that water fraction has little impact on TBR, which is an important factor related to blanket tritium efficiency. It indicated that TBR value of each Pn would be similar under the two kinds of water conditions, but PWR case is a little higher than that of SCWRʹs. In addition, it was found that beryllium is the dominant factor leading a higher TBR inside blanket. As a result, TBR is an insensitive value with the water condition variation. The results would be important to water condition choice for solid blanket in the future.