CSNI1021 PHEBUS/TEST-218.

1. NAME OF EXPERIMENT:  PHEBUS/test-218.

3. DESCRIPTION OF TEST FACILITY

PHEBUS test facility operated at CEA Research Center CADARACHE consists of a pressurized circuit involving pumps, heat exhangers and a blowdown tank
- 25 nuclear fuel rod bundle, coupled to a separate driver core
- active length 0.8 m, cosine axial power profile
- pressurized and unpressurized fuel rods
- controlled cooling conditions at the bundle inlet (blowdown, refill and reflood period)
- depressurized test rig volume 0.22 m3
  
The following "as measured" boundary conditions (B.C.) were offered to participants as options with decreasing challenge to their analytical approach:
Boundary conditions B.C.0:
- full thermal-hydraulic analysis of PHEBUS test rig (was not recommended!)
Boundary conditions B.C.1:
- thermal power level of fuel bundle
- fluid inlet conditions to bundle section
Boundary conditions B.C.2:
- local cladding temperatures of rods
- heat transfer coefficients
Boundary conditions B.C.3:
- cladding temperatures of rods
- internal pressure of rods

4. DESCRIPTION OF TEST

Post-test investigation into the response of a nuclear fuel bundle to a large break loss of coolant accident with respect to
- local fuel temperatures,
- cladding strain at the time of burst,
- time to burst and
under given thermal-hydraulic boundary conditions of PHEBUS-test 218

6. PHENOMENA TESTED

Behaviour of a Fuel Rod Bundle during a Large Break LOCA Transient with a two Peaks Temperature History.

8. RELATED OR AUXILIARY PROGRAMS: COUNTERPART EXPERIMENTS

- E. Scott de Martinville, M. Pignard:
Behaviour of a Fuel Rod Bundle during a Large Break LOCA Transient with a two
Peaks Temperature History (PHEBUS Experiment) - Final Comparison Report ISP 19
(CSNI Report No. 131) 1987

11. TEST DESIGNATION:  test-218.

15. ESTABLISHMENT:  
CEA/CEN-Cadarache,
IPSN/DERS/SEAREL, France

Documentation in PDF format