ERSEC Tube (Inside) (SET facility)

CCVM Key:
3.12
Country:
France
Organization:
CEA - Commissariat à l'énergie atomique
Operating years:
-
Reference reactor:
Westinghouse PWR ;; FRAMATOME PWR
Availability:
Dismantled
Objectives:
Study thermal behaviour during reflooding in a simple test section with given boundary and initial conditions
Pictures:
SET21 picture #1 (PNG)

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:

Keywords Steam Separator:

Keywords Others:

Components details:

Tube is made of inconel 600 and its dimensions are : - Heated length : 3.325m - Inner diameter : 12.10^-3 m - outer diameter : 14.10^-3 m

References

  • P. Clement, et al.: "Refroidissement de secours des reacteurs a eau legere. Essais de nenoyage en geometrie tubulaire". Note CEA, Service des Transferts Thermiques TT no. 156, April 1979

  • ERSEC, investigation of the reflooding phase of a Loss of Coolant Accident


Phenomena

Relevance Phenomenon
100%
Heat Transfer : Core
100%
Heat Transfer : SG
50%
Quench Phenomena