CSNI0072 PKL/K9.
PKL/K9, Refill and Reflood Experiment in a Simulated PWR Primary System (PKL)
NAME OR DESIGNATION, COMPUTER, DESCRIPTION OF TEST FACILITY, DESCRIPTION OF TEST, RESTRICTIONS, PHENOMENA TESTED, FEATURES, AUXILIARIES, STATUS, REFERENCES, TEST DESIGNATION, LANGUAGE, ESTABLISHMENT, MATERIAL, CATEGORIES
[ top ]
[ top ]
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 |
|---|---|---|---|
| PKL/K9 | CSNI0072/01 | Report | 01-APR-1981 |
Machines used:
No item found
[ top ]
3. DESCRIPTION OF TEST FACILITY
PKL-facility simulates the essential primary system components of a typical West German 1300 PWR with regard to their thermohydraulic behaviour. The facility essentially consists of the pressure vessel with the heated bundle, the downcomer simulator, the primary loops with the components steam generator and pump simulator, the injection devices, the break geometry simulator, as well as the separators connected thereto, and the test containment to maintain a back-pressure at the location of break which is expected to be typical for emergency conditions. The number of heater rods and the cross-sections of the testing plant are on a reduced scale 1:134 in comparison with a typical German PWR. The elevations and locations are essentially full scale.
Pressure vessel
---------------
The space between the pressure vessel and the inner core casing is sealed from the core region and the upper and lower plenum and connected with the upper plenum only by a pressure equalization line. The rod bundle surrounded by the inner core casing consists of 340 rods, 337 of which are indirect electrically heated. The test bundle cross-section as well as a heater element with the measuring elevations, the original-KWU-spacers and the axial power profile (7 power steps) are described.
Downcomer
---------
The downcomer is simulated by the downcomer nozzle region and the downcomer U-tube. The cold leg injection takes place both directly in the downcomer nozzle region and in the lines of t he intact single and double loop near to the downcomer nozzle region. A cylindrical insertion and repulsing metal sheets are installed in the downcomer nozzle region in order to avoid the emergency injection points into the broken loop.
PKL-facility simulates the essential primary system components of a typical West German 1300 PWR with regard to their thermohydraulic behaviour. The facility essentially consists of the pressure vessel with the heated bundle, the downcomer simulator, the primary loops with the components steam generator and pump simulator, the injection devices, the break geometry simulator, as well as the separators connected thereto, and the test containment to maintain a back-pressure at the location of break which is expected to be typical for emergency conditions. The number of heater rods and the cross-sections of the testing plant are on a reduced scale 1:134 in comparison with a typical German PWR. The elevations and locations are essentially full scale.
Pressure vessel
---------------
The space between the pressure vessel and the inner core casing is sealed from the core region and the upper and lower plenum and connected with the upper plenum only by a pressure equalization line. The rod bundle surrounded by the inner core casing consists of 340 rods, 337 of which are indirect electrically heated. The test bundle cross-section as well as a heater element with the measuring elevations, the original-KWU-spacers and the axial power profile (7 power steps) are described.
Downcomer
---------
The downcomer is simulated by the downcomer nozzle region and the downcomer U-tube. The cold leg injection takes place both directly in the downcomer nozzle region and in the lines of t he intact single and double loop near to the downcomer nozzle region. A cylindrical insertion and repulsing metal sheets are installed in the downcomer nozzle region in order to avoid the emergency injection points into the broken loop.
[ top ]
4. DESCRIPTION OF TEST
Test K 9 out of a series PKL-IB was conducted on May 30, 1979 by Kraftwerk Union (KWU) at Erlangen (Germany).
The objective of the integral cold leg injection test K 9 (double-ended 200%-break) was to investigate after a LOCA the refill and reflood process within a pressure vessel considering the influence of the simulated primary loops of a pressurized water reactor (PWR). As to the number of rods and the cross-sections of vessel and components the PKL test-facility is scaled down to 1:134 of a typical West Germany PWR. The elevations and locations have been designed in order to reproduce substantially the original extension. Compared to other cold leg injection tests in the same facility (K5. 3a, K5. 4a) test K9 differs in a uniform radial power profile in the core, an increased temperature of injected Emergency Core Cooling (ECC) water (feed water, from 35 to 53 deg.C), an injection mass flow rate highly reduced to 1:3, and a history of it corresponding to that of a typical US-PWR, on the average somewhat higher maximum initial temperatures in the bundle, and a smaller bundle heating power during the initial phase.
Test K 9 out of a series PKL-IB was conducted on May 30, 1979 by Kraftwerk Union (KWU) at Erlangen (Germany).
The objective of the integral cold leg injection test K 9 (double-ended 200%-break) was to investigate after a LOCA the refill and reflood process within a pressure vessel considering the influence of the simulated primary loops of a pressurized water reactor (PWR). As to the number of rods and the cross-sections of vessel and components the PKL test-facility is scaled down to 1:134 of a typical West Germany PWR. The elevations and locations have been designed in order to reproduce substantially the original extension. Compared to other cold leg injection tests in the same facility (K5. 3a, K5. 4a) test K9 differs in a uniform radial power profile in the core, an increased temperature of injected Emergency Core Cooling (ECC) water (feed water, from 35 to 53 deg.C), an injection mass flow rate highly reduced to 1:3, and a history of it corresponding to that of a typical US-PWR, on the average somewhat higher maximum initial temperatures in the bundle, and a smaller bundle heating power during the initial phase.
[ top ]
[ top ]
6. PHENOMENA TESTED
There are numerous measuring points for determination of thermohydraulic phenomena in the pressure vessel and in the loops.
The following important variables are measured:
- cladding tube temperature
- fluid temperature
- wall temperature
- absolute pressure
- differential pressure
- flow rate
- heating power
All of the 300 measured quantities connected with a data acquisition system and a process computer during the test are recorded once a second, which is sufficient for determination of the history of the refill and reflood process.
There are numerous measuring points for determination of thermohydraulic phenomena in the pressure vessel and in the loops.
The following important variables are measured:
- cladding tube temperature
- fluid temperature
- wall temperature
- absolute pressure
- differential pressure
- flow rate
- heating power
All of the 300 measured quantities connected with a data acquisition system and a process computer during the test are recorded once a second, which is sufficient for determination of the history of the refill and reflood process.
[ top ]
[ top ]
[ top ]
CSNI0072/01, included references:
- D.L. Nguyen and W. Winkler:Comparison Report on OECD-CSNI Loca Standard Problem No.10:
Refill and Reflood Experiment in a Simulated PWR Primary System (PKL)
CSNI Report No.64 (DRAFT) April 1981
[ top ]
[ top ]
Keywords: experiment, loss-of-coolant accident, pressurized water reactor, primary, reflooding.