CSNI2000: SETH/PKL III, Countermeasures for 2 types of PWR accidents, Gas flow distributions relevant to in-reactor containments

Program-name Package-ID Status SETH/PKL III E1.1 CSNI2000/01 Obsolete SETH/PKL III E2.1 CSNI2000/02 Obsolete SETH/PKL III E2.1 CSNI2000/03 Obsolete SETH/PKL III E2.2 CSNI2000/04 Obsolete SETH/PKL III E2.2 CSNI2000/05 Obsolete SETH/PKL III E2.3 CSNI2000/06 Obsolete SETH/PKL III E3.1 CSNI2000/07 Obsolete SETH/PKL III E3.1 CSNI2000/08 Obsolete SETH/PKL III FINAL CSNI2000/09 Arrived

Machines used: Package-ID Orig.Computer Test Computer CSNI2000/09

3. DESCRIPTION OF THE PROJECT -
The SETH Project covers two aspects of accident management:

- Countermeasures for two types of Pressurised Water Reactor (PWR) accidents - carried at the PKL/Siemens establishment in Erlangen, Germany;

- Gas flow distributions relevant to in-reactor containments (with focus on simulated hydrogen distribution) - carried out at the PSI/PANDA establishment near Zurich, Switzerland.

The SNP/ PKL tests investigate two PWR safety issues: boron dilution in loss of coolant accidents and boron dilution during mid-loop operation (shutdown conditions). The first category of tests verifies if conditions can arise for core reactivity insertion due to boron dilution during a small-break loss of coolant accidents and with a natural circulation restart. The second test series assesses primary circuit accident management operations to prevent boron dilution as a consequence of loss of heat removal in mid-loop operation conditions.

The PSI/PANDA experiments provide data on containment three-dimensional gas flow and distribution issues that are important for code prediction capability improvements, accident management and design of mitigating measures. These experiments were conducted on a large scale in multi-compartment geometries in order to provide data suitable for the improvement and validation of safety analysis codes.

The NEA Committee for the Safety of Nuclear Installations (CSNI) has been promoting international initiatives and collaborations to establish convincing experimental safety programmes around specific facilities. As a first step in this direction, the PKL (Pressurised Water Reactor) loop in Germany and the PANDA in Switzerland were requested to develop proposals consistent with the priorities indicated in the CSNI Senior Group of Experts on Safety Research (SESAR) report Nuclear Safety Research in OECD Countries: Summary Report of Major Facilities and Programmes at Risk. Their proposals, after discussions with Member country experts, formed the basis for the SETH Project (see also SETH/PANDA CSNI2002/01).

The large-scale test facility PKL is a scaled-down model of a pressurized water reactor of KWU design of the 1300 MW class. Reference plant is the Philippsburg 2 nuclear power plant. The PKL test facility models the entire primary side and essential parts of the secondary side (without turbine and condenser) of the reference plant.

The 4 tests on inherent boron dilution during SB-LOCA were:
- E1.1 (break in hot leg, HPSI into all 4 cold legs)
- E2.1 (break in hot leg, HPSI into all 4 hot legs)
- E2.2 (break in cold leg, HPSI into 2 cold legs)
- E2.3 (break in hot leg, HPSI into 2 hot legs)
- Test E3.1 (loss of RHRS in shutdown plant) was conducted utilizing boric acid and boron concentration measuring technique.

Project participants:
Belgium, Czech Republic, Finland, France, Germany, Hungary, Italy, Japan, Republic of Korea, Spain, Sweden, Switzerland, Turkey, United Kingdom, United States.
Project period : April 2001-June 2005

For more information see: http://www.nea.fr/html/jointproj/pkl.html   and
http://www.nea.fr/html/dbprog/ccvm/csni-rest.html

9. STATUS
CSNI2000/01: 06-APR-2005 Obsolete
CSNI2000/02: 10-MAY-2004 Obsolete
CSNI2000/03: 06-APR-2005 Obsolete
CSNI2000/04: 10-MAY-2004 Obsolete
CSNI2000/05: 06-APR-2005 Obsolete
CSNI2000/06: 06-APR-2005 Obsolete
CSNI2000/07: 11-MAR-2004 Obsolete
CSNI2000/08: 06-APR-2005 Obsolete
CSNI2000/09: 01-MAR-2006 Masterfiled restricted

10. REFERENCES -
- Report No. FANP TGT1/02/47 in German
CSNI2000/09:
- K. Umminger, T. Mull, B. Schoen:
Final Report of the PKL Experimental Program within the OECD/SETH Project
FANP NGTT1/04/en/04 (December 2004)
- H. Kremin, H. Limprecht, R. Guneysu, K. Umminger:
Description of the PKL III Test Facility
FANP NT31/01/e30 (July 2001)
- H. Kremin, H. Limprecht, R. Guneysu:
Determination of Masses in the PKL Test Facility
FANP NT31/01/e34 (August 2001)
- H. Kremin, H. Limprecht, R. Guneysu:
Determination of Pressure Losses in the PKL Test Facility
FANP NT31/01/e39 (September 2001)
- H. Kremin, H. Limprecht, R. Guneysu:
Determination of Thermal Losses in the PKL Test Facility
FANP NT31/01/Exx (August 2001)
- H. Kremin, H. Limprecht, R. Guneysu:
Determination of Individual Volumes and of Total Volume
in the PKL Test Facility
FANP NT31/01/e33 (August 2001)
- K. Umminger, T. Mull, B. Schoen:
Experiments on Boron Dilution in the Integral Test Facility PKL
The 10th Int. Topical Meeting on Nuclear Reactor
Thermal Hydraulics (NURETH-10) Seoul, Korea, October 5-9, 2003
- K. Umminger and B. Brand:
Integral Tests Conducted at the PKL Test Facility on Topical
PWR Safety Issues
- K. Umminger, R. Mandl, R. Wegner and M. Perst:
Restart of Natural Circulation in a PWR - PKL Test Results and
S-RELAP5 Calculations -
- B. Schoen and K. Umminger:
Test PKL III E2.1: Inherent Boron Dilution during SB-LOCA (Break 40 cm2/145 in
Hot Leg of PRZ Loop, ECC Injection by 4 SIPs into Hot Legs and 4 LP Pumps into
Hot Legs, Cooldown at 100 K/h)
FANP TGT1/02/en/11 (December 2002)
- T. Mull and K. Umminger:
Test PKL III E2.2: Inherent Boron Dilution during SB-LOCA (Break: 32 cm2/145 in
Cold Leg, ECC Injection by 2 HPSI Pumps into Cold Legs and 2 LPSI Pumps into
Cold Legs, Cooldown at 100 K/h)
FANP TGT1/02/en/44 (December 2002)
- B. Schoen, K. Umminger:
Test PKL III E2.3: Inherent Boron Dilution during SB-LOCA (Break: 50 cm2/145 in
Hot Leg, ECC Injection by 2 SIPs into Hot Legs and 4 ACCs into Hot Legs,
Cooldown at 100 K/h) without Breakdown of Natural Circulation in the Loops Fed
by SIPs
FANP TGT1/03/en/47 (December 2003)
- B. Schoen, K. Umminger:
Test PKL III E3.1
Loss of Residual Heat Removal in 3/4 Loop Operation with the Reactor Coolant
System Closed
FANP TGT1/03/en/10 (December 2003)

11. HARDWARE REQUIREMENTS - The monitor resolution has to be set with 1280 x 1024 pixels.

12. PROGRAMMING LANGUAGE -CSNI2000/09:

13. SOFTWARE REQUIREMENTS -
- Adobe Acrobat Reader for printing and reading the measurement list, the measurement plans and the plot sheets.
- Microsoft Excel for reading the measured test data.

15. NAME AND ESTABLISHMENT OF AUTHORS -
Klaus Umminger
PKL Project Manager
Framatome ANP GmbH
FANP NGTT1
Freyeslebenstrasse 1
91058 Erlangen
Germany
Thomas Mull
Evaluation and documentation of tests
Freyeslebenstrasse 1
91058 Erlangen
Germany

16. MATERIAL AVAILABLE -CSNI2000/09:
PKL Descriptions (PDF files)
Results for tests E1.1, E2.1, E2.2, E2.3, and E3.1
RELAP5MOD3 input files
Handouts
Publications

17. CATEGORIES -

- Y. Integral Experiments Data, Databases, Benchmarks

Keywords: BORON, GAS FLOW, LOSS-OF-COOLANT ACCIDENT, PRESSURIZED WATER REACTOR