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Safety analysis of supercritical-pressure light-water cooled reactor with water rods Yoshiaki Oka April 2003, GIF SCWR Mtg. at Madison.

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Presentation on theme: "Safety analysis of supercritical-pressure light-water cooled reactor with water rods Yoshiaki Oka April 2003, GIF SCWR Mtg. at Madison."— Presentation transcript:

1 Safety analysis of supercritical-pressure light-water cooled reactor with water rods Yoshiaki Oka April 2003, GIF SCWR Mtg. at Madison

2 SCLWR-H plant system

3 Flow rate low Level 1 Reactor scram Level 2 AFS Level 3 MSIV/ADS/LPCI system Pressure low Level 1 Reactor scram Level 2 MSIV/ADS/LPCI system Pressure high Level 1 Reactor scram Level 2 SRV AFS: auxiliary feedwater system MSIV: main steam isolation valve ADS: automatic depressurization system LPCI: low pressure core injection system

4 Capacity: RCIC(AFS) TD 1 unit: 4%/unit AFS TD 2 units: 4%/unit ADS 8 units: 20%/unit at 25MPa LPCI MD 3 units: 150kg/s/unit at 1.0MPa Configuration: TD- RCIC LPCI/RHR TD-AFS LPCI/RHR RCIC: reactor core isolation cooling system RHR: residual heat removal system

5 Accidents 1Total loss of feedwater 2Reactor coolant pump seizure 3Control rod ejection at normal operation 4Control rod ejection at hot standby 5Control rod ejection at cold standby Transients 6Loss of feedwater heating 7Inadvertent startup of AFS 8Partial loss of feedwater 9Loss of offsite power 10Loss of load with turbine bypass 11Loss of load without turbine bypass 12Control rod withdrawal at normal operation 13Control rod withdrawal at hot standby 14Feedwater control system failure 15Pressure control system failure

6 Total loss of feedwater accident

7 Coast-down time [s]12345 PCT [ ℃ ] 974934890859833 AFS capacity [%/unit]12346 PCT [ ℃ ] 872857856833816 AFS delay [s]31030 PCT [ ℃ ] 833902904 PCT: peak cladding temperature Total loss of feedwater accident

8 Loss of load without turbine bypass transient

9

10 Ratio of coolant density coefficient 0.511.31.5 Maximum pressure [MPa] 26.8 27.628.7 Maximum power [%] 114154419887 Peak cladding temperature [ ℃ ] 7077278731040 SRV setpoint [MPa]26.026.226.5 Maximum pressure [MPa]26.626.827.2 Maximum power [%]135157177 Peak cladding temperature [ ℃ ] 698727652 PCT: peak cladding temperature Loss of load without turbine bypass transient

11

12 Transients PCT [ ℃ ]Over 670 ℃ Over 700 ℃ Loss of feedwater heating6711.5 s- Partial loss of flow7024.5 s1.0 s Loss of load (no-bypass)7270.5 s0.3 s PCT: Peak Cladding Temperature Durations of high cladding temperature

13 Result – 100% hot leg break (blowdown)

14

15 Result – 100% Cold leg break (blowdown)

16 LPCI 容量 (kg/s/unit) 100150300400800 被覆温度 ( ℃ ) 1190930800690650

17 T = 0 sec : Scram, T = 1 sec : ADS Core power does not exceed 100%. Cladding temperature does not exceed that of normal operation. Depressurization cools the core effectively

18 T = 0 sec : ADS, T = 0.55 sec : Scram Core power increases to 160% before scram. But cladding temperature does not exceed that of normal operation because core flow rate is higher.

19 Summary of the results Total loss of flow accident: maximum cladding temperature stays low, 833C (margins to the limit 1260C) Overpressurization transient without turbine bypass shows 50% power rise and Tc reaches 727C, (margins to the limit 800C ) Duration of high cladding temperature is short less than 5 sec. Potential for improvement of fuel integrity criteria at transients. Hot leg break LOCA gives rise to reactivity insertion. But Tc reaches only 550C. Core flow is induced by depressurization due to the once-through coolant cycle. Cold leg break LOCA, Tc reaches 930C, (margins to the limit 1260C) Depressurization cools the core effectively


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