• Home
• About Us
  • What's New
  • Press Room
  • Contacts
  • Vacancies
  • Practical Info
  • Register
  • Web Links
  • List of Acronyms
• Work Areas
  • Nuclear Safety
  • Radioactive Waste
  • Radiological Protection
  • Nuclear Development
  • Nuclear Science
  • Nuclear Law 
  • Joint Projects
  • Sustainable Development
  • Civil Society
• Data Bank
  • Nuclear Data 
  • TDB Project 
  • Computer Programs
• Publications
  • By Subject 
  • Recently Published
  • NEA News
  • Policy Papers
• Press Room
• Search

[Program Service | Recent programs]

CSNI1022 REBEKA. (Abstract last modified 01-FEB-1985)


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

---

Abstract Table of Contents:

NAME | COMPUTER | PROBLEM | SOLUTION | RESTRICTIONS | CPU | FEATURES | AUXILIARIES | STATUS | REFERENCES | REQUIREMENTS | LANGUAGE | OPERATING SYSTEM | OTHER RESTRICTIONS | AUTHOR | MATERIAL | CATEGORIES |

---

1. NAME OF EXPERIMENT - REBEKA.


2. COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE -

To request or retrieve programs click on the one of the active versions below. A password and special authorization is required.

Explanation of the status codes.

Program-name         Package-ID  Status
REBEKA               CSNI1022/01 Report

Machines used:
Package-ID     Orig.Computer                       Test Computer
CSNI1022/01                                        

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)


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.


6. PHENOMENA TESTED - Behaviour of a Fuel Bundle Simulator during a Specified Heatup and Flooding Period.


7. SPECIAL FEATURES OF EXPERIMENTS -


8. COUNTERPART EXPERIMENTS -


9. STATUS
CSNI1022/01: 01-FEB-1985 Report Only


10. REFERENCES  - 
CSNI1022/01:
- 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


11. TEST DESIGNATION - REBEKA


12. PROGRAMMING LANGUAGE -CSNI1022/01: 


15. ESTABLISHMENT - 
Inst. For Reactor Dynamics and Reactor Safety,
Techn. Univ. Munich, Germany


16. MATERIAL AVAILABLE -CSNI1022/01:
Documentation in PDF format


17. CATEGORIES  - 

- Y. Integral Experiments Data, Databases, Benchmarks


Keywords: CLADDING, FLOODING, FUEL BUNDLE, HEATING, NON-STEADY

---

Home - About Us - Work Areas - Data Bank - Publications - Press Room - List of acronyms - Search