To ensure a structural integrity of a feed water nozzle by suppressing a temperature fluctuation in an annular flow path between a thermal sleeve and a feed water nozzle even for mixing core water and feed water with a large temperature difference at the feed water nozzle part in an operation method for removing heat by lowering feed water temperature without increasing steam flow generating from a reactor when a reactor core thermal power increases in a reactor power generation system and suppressing the occurrence of high cycle thermal fatigue caused by the temperature fluctuation due to thermal stratification.
The feed water nozzle 13, attached to the reactor pressure vessel 1 of a nuclear power generation system and connected with the feed water system, forms a double tube structure having a thermal sleeve 14 inside the feed water nozzle 13. The relation between the gap δ of an annular flow path 16 formed between the outer surface of the thermal sleeve 14 and a feed water nozzle inner surface 13a and the inner diameter Di is δ/Di≤0.03.
| JPS5416090 | COOLING WATER PIPING STRUCTURE OF REACTOR PRESSURE VESSEL |
| JPH01237491 | PIPING FOR FEED LIQUID |
| WO/2008/073014 | JET PUMP RISER CLAMP |
AOYAMA TADAO
OTSUKA MASAYA
CHAGI MASAO
KITO KAZUAKI
Manabu Inoue