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NEA-0839 DRUFAN-01/MOD2.

DRUFAN-01/MOD2, Transient Thermohydraulics of PWR Primary System LOCA

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1. NAME OR DESIGNATION OF PROGRAM:  DRUFAN-01/MOD2.
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2. COMPUTERS
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Program name Package id Status Status date
DRUFAN-01/MOD2 NEA-0839/02 Tested 13-DEC-1982

Machines used:

Package ID Orig. computer Test computer
NEA-0839/02 IBM 3033 IBM 3033
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3. DESCRIPTION OF PROBLEM OR FUNCTION

DRUFAN is an advanced best estimate code for simulation of the transient thermal hydraulic behaviour during PWR-blowdown with large break size.
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4. METHOD OF SOLUTION

The code is based on the lumped parameter approach and allows flexible control volume configurations. The physical model takes into account thermodynamic nonequilibrium. Using finite difference techniques a 1-dimensional representation of the discharge flow path including geometrical influences is possible.
The physical model is based on separated field equations for liquid  and vapour mass and overall field equations for energy and momentum. The mass transfer rates between phases during evaporation and condensation are based on correlations for the controlled growth and shrinkage of vapour bubbles or liquid droplets, respectively.
A heat conductor model based on the energy transport equation is available for simulation of structures, electrical heater rods and fuel rods. For the heat transfer between solid structures and the fluid a comprehensive package of flow regime dependent heat transfer and critical heat flux correlations can be used. Simulation of components (valve, pressurizer, accumulator, pump, steam generator)  is possible with functions or models. Power generation in solid structures may be simulated by an input time function, an electrical heater model or a neutron kinetics models.
As a result of the lumped parameter approach a set of ordinary differential equations is obtained from the field equations. These equations, together with those resulting from the simulation of critical discharge flow near the outlet by a finite difference method, are solved by an explicit/implicit integration method with automatic time step, order and error control. The ordinary differential equations representing heat conductors are solved by an essentially implicit integration method.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

   - Vapour or liquid phase are assumed to be saturated.
   - A homogeneous mixture of liquid and vapour is assumed.
     (Exception: pressurizer, accumulator)
   - Phase separation is not taken into account.
   - The fluid properties are limited to a range of 0.1 to 180 bar.
- The code is suitable for thermal hydraulic problems where phase  separation effects can be neglected (e.g. blowdown with large      break size).
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6. TYPICAL RUNNING TIME

Simulation of SEMISCALE Experiment S60-3 with 24 control volumes, 30 flow path and 18 heat conductors:
Problem time:    24 sec
Running time:  1800 sec on AMDAHL 470 V/6 II
NEA-DB required the following times to execute the test case:
LOBI test case:     150 seconds
Restart case:       100 seconds.
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7. UNUSUAL FEATURES OF THE PROGRAM

   - variable dimensioning possible
   - steady state initialization
   - restart capability
   - printer plot generation available.
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8. RELATED AND AUXILIARY PROGRAMS

   - program BLDAPROG for generation of BLOCKDATA routine
- program DRUCDR for generation of 1-D critical discharge rate      table
   - plot programs (POLYPLOT, DISSPLA).
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9. STATUS
Package ID Status date Status
NEA-0839/02 13-DEC-1982 Tested at NEADB
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10. REFERENCES

- K. Wolfert,
  "Die Beruecksichtigung thermodynamischer Nichtgleichgewichts-
  Zustaende bei der Simulation von Druckabsenkungsvorgaengen",
Dissertation an der TU Muenchen, 5.e.1979 (Preliminary Volume III)  - M.J. Burwell,
  Overview and Verification of DRUFAN-01/MOD2,
  GRS-A-715, May 1982.
NEA-0839/02, included references:
- M.J. Burwell, D Enix, G. Lerchl and F. Steinhoff:
  Program Description - System Code.  GRS-A-646 (November 1981)
- M.J. Burwell and D. Enix:
  Program Description - Supporting Codes. GRS-A-654  (December 1981)
- R.T. Jensen:
  Assessment.  GRS-A-660  (December 1981)
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11. MACHINE REQUIREMENTS:  1110 kbytes of main storage on IBM 3033.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0839/02 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
OS370/033 (IBM 3033).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

Maximum number of lumped parameter control volumes = 170.
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15. NAME AND ESTABLISHMENT OF AUTHOR

M.J. Burwell, G. Lerchl, F. Steinhoff, K. Wolfert,
Gesellschaft fuer Reaktorsicherheit (GRS) mbH
Forschungsgelaende
8046 Garching (Federal Republic of Germany)
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16. MATERIAL AVAILABLE
NEA-0839/02
File name File description Records
NEA0839_02.003 DRUFAN-01/MOD2 INFORMATION FILE 234
NEA0839_02.004 BLOCK DATA GENERATION PROGRAM (FORTRAN-4) 757
NEA0839_02.005 INPUT FOR BLOCK DATA GENERATION PROGRAM 1078
NEA0839_02.006 JCL TO RUN BLOCK DATA GENERATION PROGRAM 48
NEA0839_02.007 OUTPUT OF BLOCK DATA GEN. PGM. ON FT08 1506
NEA0839_02.008 OUTPUT OF BLOCK DATA GEN. PGM. ON FT06 1552
NEA0839_02.009 DRUCDR SOURCE (FORTRAN-4) 3528
NEA0839_02.010 DRUCDR INPUT FOR SIX TEST CASES 93
NEA0839_02.011 DRUCDR JCL FOR EXECUTION 60
NEA0839_02.012 DRUCDR OUTPUT (FT15) OF SIX TEST CASES 1626
NEA0839_02.013 DRUCDR OUTPUT (FT06) OF SIX TEST CASES 13647
NEA0839_02.014 DRUFAN SOURCE (FORTRAN-4) 28393
NEA0839_02.015 LOBI SAMPLE, BLOCK DATA SOURCE 753
NEA0839_02.016 LOBI SAMPLE, START RUN JCL 120
NEA0839_02.017 LOBI SAMPLE, START RUN INPUT DATA 1390
NEA0839_02.018 LOBI SAMPLE, START RUN OUTPUT (FT06) 4532
NEA0839_02.019 LOBI SAMPLE, RESTART RUN JCL 92
NEA0839_02.020 LOBI SAMPLE, RESTART RUN INPUT DATA 1392
NEA0839_02.021 LOBI SAMPLE, RESTART RUN OUTPUT (FT06) 3657
NEA0839_02.022 BRS SAMPLE, BLOCK DATA SOURCE 751
NEA0839_02.023 BRS SAMPLE, JCL 110
NEA0839_02.024 BRS SAMPLE, INPUT DATA 92
NEA0839_02.025 BRS SAMPLE, OUTPUT (FT06) 5371
NEA0839_02.026 CSP SAMPLE, BLOCK DATA SOURCE 751
NEA0839_02.027 CSP SAMPLE, JCL 111
NEA0839_02.028 CSP SAMPLE, INPUT DATA 585
NEA0839_02.029 CSP SAMPLE, OUTPUT (FT06) 3456
NEA0839_02.030 CANON SAMPLE, BLOCK DATA SOURCE 751
NEA0839_02.031 CANON SAMPLE, JCL 111
NEA0839_02.032 CANON SAMPLE, INPUT DATA 500
NEA0839_02.033 CANON SAMPLE, OUTPUT (FT06) 4941
NEA0839_02.034 EDW SAMPLE, BLOCK DATA SOURCE 744
NEA0839_02.035 EDW SAMPLE, JCL 111
NEA0839_02.036 EDW SAMPLE, INPUT DATA 643
NEA0839_02.037 EDW SAMPLE, OUTPUT (FT06) 2465
NEA0839_02.038 FDW SAMPLE, BLOCK DATA SOURCE 753
NEA0839_02.039 FDW SAMPLE, JCL 111
NEA0839_02.040 FDW SAMPLE, INPUT DATA 475
NEA0839_02.041 FDW SAMPLE, OUTPUT (FT06) 1549
NEA0839_02.042 SEMISCALE SAMPLE, BLOCK DATA SOURCE 753
NEA0839_02.043 SEMISCALE SAMPLE, JCL 111
NEA0839_02.044 SEMISCALE SAMPLE, INPUT DATA 1182
NEA0839_02.045 SEMISCALE SAMPLE, OUTPUT (FT06) 4650
NEA0839_02.046 RTEMPS SOURCE TO REPLACE ITIME (ASSEMBLER) 64
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis
  • H. Heat Transfer and Fluid Flow

Keywords: hydrodynamics, loss-of-coolant accident, pwr reactors, reactor dynamics, reflooding, thermodynamics, transients.