CSNI0071 DOEL2/SGTR.

1. NAME OR DESIGNATION:  DOEL2/SGTR.

3. DESCRIPTION OF TEST FACILITY

DOEL 2 is a Westinghouse, 2 loop pressurized water reactor (PWR) rated at 392 Mwe (NET) and commissioned in 1975, for which TRACTEBEL was the architect/engineer. This plant located in Belgium in part of the twin concept with DOEL 1, as they share some common engineered safety systems such as the high pressure safety injection system (HPSI).

4. DESCRIPTION OF TEST

Data measured during the Steam Generator Tube Rupture (SGTR) incident on full scale facility are available.

5. EXPERIMENTAL LIMITATIONS OR SHORTCOMINGS

Quantity and quality of available data from real plants are usually inferior to well instrumented test facility data.
  
Higher uncertainties in the plant initial and boundary conditions.

6. PHENOMENA TESTED

Recorded parameters:
- Temperatures (the precision of the temperature sensors is estimated at about 1.5%)
- Primary pressure (the precision of the pressure sensors is estimated at +/- 2 bar at the nominal system pressure resulting in an uncertainty of 1.3%)
- Pressuriser level (the uncertainty band for the level gauge is estimated at 5%)
- steam generator pressure (the sensors are located just upstream of the main steam isolation valves. The tolerance on the S.G. pressure gauges is estimated at 3%)
- steam generator water level (narrow range) (the tolerance on the S.G. level gauges is estimated at 16%).

8. RELATED OR AUXILIARY PROGRAMS: COUNTERPART EXPERIMENTS

- M. De Feu, M. Firnhaber, R. Pochard, E. Stubbe:
International Standard Problem-20, Steam Generator Tube Rupture
Nuclear Power Plant DOEL 2 - Belgium, CSNI Report No. 154 (1988)

11. TEST DESIGNATION:  SGTR

15. ESTABLISHMENT

TRACTEBEL ENERGY ENGINEERING
Avenue Ariane 7
B-1200 BRUSSELS