last modified: 26-FEB-1992 | catalog | categories | new | search |

NESC9978 COBRA-3C/RERTR.

COBRA-3C/RERTR, Thermohydraulic Low Pressure Subchannel Transients Analysis

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1. NAME OR DESIGNATION OF PROGRAM:  COBRA-3C/RERTR.
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2. COMPUTERS
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Program name Package id Status Status date
COBRA-3C/RERTR NESC9978/01 Tested 26-FEB-1992

Machines used:

Package ID Orig. computer Test computer
NESC9978/01 IBM 370 series IBM 3090
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3. DESCRIPTION OF PROGRAM OR FUNCTION

COBRA-3C/RERTR is a modification of the COBRA-3C/MIT, thermal-hydraulic nuclear reactor  subchannel analysis program for research and test reactors (RERTRs). Which are operated at low pressure and low temperatures and may use  plate-type fuel elements and heavy water as coolant. COBRA-3C/RERTR  incorporates critical heat flux correlations suitable for low-pressure systems, flow instability correlations, two-phase heat  transfer coefficients suitable for research and test reactors, thermodynamic properties of heavy water, the capability of calculating the thickness of oxide film on an aluminum fuel plate, and the void fraction model based on the Bowring bubble detachment criterion. A plotting capability is included to display transient results.
The program calculates the steady-state power margins for reactors using either rod- or plate-type fuel elements. For the rod-type fuel the power margin is limited by surface clad temperature based on subcooled nucleate boiling heat transfer. For the plate-type fuel the power margin is limited by the flow instability rate (FIR), which is defined as the ratio of the reactor power at which the flow instability will occur to the operating power. The program is also capable of calculating the limiting thermal-hydraulic parameters in a RERTR for both loss-of-flow and power-ramp transients. COBRA-3C/RERTR uses the proprietary ISSCO DISSPLA graphics software which is not included.
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4. METHOD OF SOLUTION:
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME:
NESC9978/01
NEA-DB ran the test cases included in this package on an IBM 3090 computer. The following execution times were required (in CPU seconds): case 1: 0.25; case 2: 0.25; case 3: 0.30; case 4:  1.27; case 5: 5.42; case 6: 9.47.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
NESC9978/01 26-FEB-1992 Tested at NEADB
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10. REFERENCES:
NESC9978/01, included references:
- Jason Chao:
  COBRA-3C/RERTR - A Thermal-Hydraulic Subchannel Code with Low
  Pressure Capabilities
  Science Applications, Inc. (December 25, 1980).
- W.L. Woodruff:
  Supplemental Information for COBRA-3C/RERTR
  ANL Applied Physics Division Memorandum (February 1983).
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11. MACHINE REQUIREMENTS:
NESC9978/01
The test cases executed on IBM 3090 in 320 Kbytes of main storage .
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC9978/01 FORTRAN+ASSEMBLER
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
NESC9978/01
MVS/DFP with compiler VS FORTRAN LEVEL 2.5.0 (IBM 3090)
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

          J. Chao and J. Matos
          Argonne National Laboratory
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16. MATERIAL AVAILABLE
NESC9978/01
File name File description Records
NESC9978_01.001 Information file 113
NESC9978_01.002 JCL examples to compile, link, execute 147
NESC9978_01.003 COBRA-3C/RERTR FORTRAN source 7930
NESC9978_01.004 COBRA-3C/RERTR ASSEMBLER source 246
NESC9978_01.006 JCL examples for COBRAPLT 27
NESC9978_01.007 COBRAPLT FORTRAN source 752
NESC9978_01.008 COBRA-3C/RERTR sample problem 1 input data 33
NESC9978_01.009 COBRA-3C/RERTR sample problem 2 input data 33
NESC9978_01.010 COBRA-3C/RERTR sample problem 3 input data 33
NESC9978_01.011 COBRA-3C/RERTR sample problem 4 input data 45
NESC9978_01.012 COBRA-3C/RERTR sample problem 5 input data 62
NESC9978_01.013 COBRA-3C/RERTR sample problem 6 input data 79
NESC9978_01.014 Sample problem 1 printed output 951
NESC9978_01.015 Sample problem 2 printed output 952
NESC9978_01.016 Sample problem 3 printed output 952
NESC9978_01.017 Sample problem 4 printed output 1250
NESC9978_01.018 Sample problem 5 printed output 3250
NESC9978_01.019 Sample problem 6 printed output 4526
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis
  • H. Heat Transfer and Fluid Flow

Keywords: advanced test reactor, fluid flow, fuel elements, heat transfer, hydraulics, reactor cores, reactor safety.