Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects
CSNI0071 DOEL2/SGTR.
last modified: 01-DEC-1988 | catalog | new | search |

CSNI0071 DOEL2/SGTR.

DOEL2/SGTR, Steam Generator Tube Rupture incident at the DOEL 2, Westinghouse 2 loop PWR

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1. NAME OR DESIGNATION:  DOEL2/SGTR.
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2. COMPUTERS

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Program name Package id Status Status date
DOEL2/SGTR CSNI0071/01 Report 01-DEC-1988

Machines used:

No specified machine
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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).
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4. DESCRIPTION OF TEST

Data measured during the Steam Generator Tube Rupture (SGTR) incident on full scale facility are available.
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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.
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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%).
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8. RELATED OR AUXILIARY PROGRAMS: COUNTERPART EXPERIMENTS
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9. STATUS
Package ID Status date Status
CSNI0071/01 01-DEC-1988 Report Only
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10. REFERENCES
CSNI0071/01, included references:
- 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)
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11. TEST DESIGNATION:  SGTR
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. ESTABLISHMENT

TRACTEBEL ENERGY ENGINEERING
Avenue Ariane 7
B-1200 BRUSSELS
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16. MATERIAL AVAILABLE
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: experimental data, pressurized water reactor, ruptures, steam generators, tubes.