last modified: 26-NOV-1998 | catalog | categories | new | search |

CSNI0061 PACTEL/ITE-06.

PACTEL-ITE06, VVER-440 natural circulation stepwise coolant inventory reduction

top ]
1. NAME OF EXPERIMENT:  PACTEL/ITE-06.
top ]
2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
PACTEL/ITE-06 CSNI0061/01 Arrived 26-NOV-1998

Machines used:

Package ID Orig. computer Test computer
CSNI0061/01 Many Computers
top ]
3. DESCRIPTION OF TEST FACILITY

PACTEL , out of pile model of VVER-440 reactor:
- 144 fuel rod simulators with electrically heated and chopped cosine axial power distribution (maximum power 1 MW)
- three double-capacity coolant loops to simulate VVER plant with six loops
- horizontally oriented secondary steam generators
- pressurizer, high and low pressure core cooling systems
  
Scaling Information:
- 1/ 305 volume and power scaled model of Russian-designed PWR of the VVER-440 type
- maximum power 1 MW equivalent to 22 % of scaled full power
- full length fuel rod simulators
- elevation of main components including loop seals preserved
- diameter (overall height) of steam generators reduced
top ]
4. DESCRIPTION OF TEST

The main goal was to study natural circulation in a VVER plant including several single- and two-phase natural circulation modes. The heat generated in the core is transported by the coolant to the steam generators. The steam generator secondary side conditions were held constant, eliminating disturbances caused by the secondary pressure variation. The primary coolant mass was reduced stepwise in the liquid form, and the amount of the drained water was given as a boundary condition. The draining period is very short compared to the stabilizing period, therefore the different natural circulation mechanisms are clearly identified. It was expected that the characteristics of natural circulation at constant pressure is mostly dependent on the primary coolant inventory and the core power level.
During the whole experiment the steam generator level control was maintained. The secondary pressure was controlled by a PI controller.
top ]
6. PHENOMENA TESTED

The objectives were:
- Study natural convection circulation in a VVER plant
- series of quasi steady natural circulation periods
- single phase natural convection and two-phase natural convection with continuous liquid flow
- convection flow under reflux -boiler mode conditions
- 'double-blind' pre-test analyses; 'open' post-test analyses also processed
top ]
7. SPECIAL FEATURES OF EXPERIMENT

Two kinds of experiments were conducted varying the end of the experiment:
A- Experiments which were terminated by switching the core power off when the core temperature started to increase.
B- Experiments which were continued by reducing the secondary pressure. The core power was switched off after the core heat-up began again.
top ]
8. RELATED OR AUXILIARY PROGRAMS: COUNTERPART EXPERIMENTS
top ]
9. STATUS
Package ID Status date Status
CSNI0061/01 26-NOV-1998 Arrived at NEADB
top ]
10. REFERENCES
CSNI0061/01, included references:
- H. Purhonen, J. Kouhia and H. Holmstrom:
ISP-33 OECD/NEA/CSNI International Standard Problem No.33
PACTEL Natural Circulation Stepwise Coolant Inventory Reduction Experiment
Comparison Report Volumes I and II (December 1994) NEA/CSNI/R(94)24
top ]
11. TEST DESIGNATION:  ITE-06.
top ]
12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
top ]
15. ESTABLISHMENT

      VTT Energy
      Nuclear Energy
      P.O. Box 1604 (Tekniikantie 4C)
      FIN-02044 VTT
      FINLAND
top ]
16. MATERIAL AVAILABLE
CSNI0061/01
Experiment ite06
NEA/CSNI/R(1994)24 Comparison report
top ]
17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: data, loss-of-coolant accident, transients.