Hydraulic analysis of the water-cooled blanket based on the sub-critical water condition

Study on the temperature control mechanism of the tritium breeding blanket for CFETR

“…This indicates that the tritium density in the blanket interior exhibits a deceasing trend from the plasma side to the outer side in the radial direction. This is consistent with previous work in which the major tritium production areas are located in the front area of the blanket module, including the cooling pipes [29,30]. However, tritium accumulation close to the cooing pipes is found in the model with the coolant.…”

Nuclear analysis of DEMO water-cooled blanket based on sub-critical water condition

“…For blanket heat transfer requirement, when the inner diameter of cooling pipe would be reduced, the coolant inlet velocity should be increased to keep the equivalent heat removal efficiency. However, for present engineering consideration, the inlet velocity of coolant need to be less than 5.5 m/s in terms of the pressure drop requirement (under 0.5 MPa) [8]. So the inlet velocity meets the consideration, the inner diameter of cooling pipe should be chosen as 9 mm at a velocity equal to 5.36 m/s.…”

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

“…Since P n varied from 1 to 5 MW/m 2 with pipe pitches change, the local TBR varied correspondingly. It was found that the trend of the local TBR profile is a non-linear decreasing distribution while P n level is rising [7], as shown in Fig. 4.…”