ERSEC Rod Bundle (SET facility)
CCVM Key:
3.13
Country:
FranceOrganization:
CEA - Commissariat à l'énergie atomique
Operating years:
-
Reference reactor:
PWR
Availability:
Dismantled
Objectives:
Main characteristics
Number of simulated fuel rods:36
Heat method:Indirect
Experimental conditions
Pressure min:0.1 MPa
Pressure max:0.6 MPa
Temperature max:600 °C
Power max:6.27 kW
Facility geometry
Keywords General:
- Non Nuclear Core
Keywords Core:
- Coolant Pump
- Rod Simulator
Keywords Steam Separator:
- Separator
- Heat exchanger (HX)
References
-
P. Clement et al.: "Refroidissement de secours des reacteurs en eau legere, essais de renoyage en grappe 6 x 6". Rapport CEA, Service des Transferts Thermiques, TT no. 157, December 1979.
-
ERSEC, investigation of the reflooding phase of a Loss of Coolant Accident
Phenomena
| Relevance | Phenomenon |
|---|---|
| Entrainment and Deentainment | |
| Quench Phenomena |