Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects
CSNI1022 REBEKA.
last modified: 01-FEB-1985 | catalog | new | search |

CSNI1022 REBEKA.

REBEKA, Behaviour of a Fuel Bundle Simulator during a Specified Heatup and Flooding Period Results

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1. NAME OF EXPERIMENT:  REBEKA.
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2. COMPUTERS
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Program name Package id Status Status date
REBEKA CSNI1022/01 Report 01-FEB-1985

Machines used:

No specified machine
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3. DESCRIPTION OF TEST FACILITY

REBEKA test facility operated at Kernforschungszentrum Karlsruhe Research Center
- 48 rod fuel simulator bundle with cosine shaped power distribution
- internal INCONEL heater rods
- standard Zircaloy-cladding
- pressurized and unpressurized fuel rod simulators
- controlled cooling conditions at the bundle inlet (blowdown, refill and reflood period)
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4. DESCRIPTION OF TEST

The test was carried of in March 1983. It consisted in investigating into the non-steady material behaviour of a bundle of electrically heated fuel rod simulators with respect to
- local fuel temperatures,
- cladding strain,
- time to burst and
- local strain at location of burst
  
Inlet coolant flow conditions and local heat transfer coefficients along the simulator bundle have been provided to participants in "open" post-test exercise to decouple analytical tasks for simulating cooling conditions and local fuel rod material behaviour.
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6. PHENOMENA TESTED

Behaviour of a Fuel Bundle Simulator during a Specified Heatup and Flooding Period.
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7. UNUSUAL FEATURES: SPECIAL FEATURES OF EXPERIMENTS
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8. RELATED OR AUXILIARY PROGRAMS: COUNTERPART EXPERIMENTS
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9. STATUS
Package ID Status date Status
CSNI1022/01 01-FEB-1985 Report Only
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10. REFERENCES
CSNI1022/01, included references:
- H. Karwat:
Behaviour of a Fuel Bundle Simulator during a Specified Heatup and Flooding
Period (REBEKA Experiment)- Results of Post-Test Analyses; Final Comparison
Report; CSNI Report No. 98; February 1985; ISP 14
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11. TEST DESIGNATION:  REBEKA
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. ESTABLISHMENT

Inst. For Reactor Dynamics and Reactor Safety,
Techn. Univ. Munich, Germany
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16. MATERIAL AVAILABLE
CSNI1022/01
Documentation in PDF format
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: cladding, flooding, fuel bundle, heating.