Computer Programs
IAEA1226 CORD-2.
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IAEA1226 CORD-2.

CORD-2, PWR Core Design and Fuel Management

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1. NAME OR DESIGNATION OF PROGRAM:  CORD-2
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2. COMPUTERS

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Program name Package id Status Status date
CORD-2 IAEA1226/03 Tested 23-MAY-1996

Machines used:

Package ID Orig. computer Test computer
IAEA1226/03 Many Computers DEC VAX 6000
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3. DESCRIPTION OF PROGRAM OR FUNCTION

CORD-2 is intended for core design applications of pressurised water reactors. The main objective was to assemble a core design system which could be used for simple calculations (such as frequently required for fuel management) as well as for accurate calculations (for example, core  design after refuelling).
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4. METHOD OF SOLUTION

The calculations are performed at the cell level with a lattice code in the supercell approximation to generate the single cell cross sections. Fuel assembly cross section homogenization is done in the diffusion approximation. Global core calculations can be done in the full three-dimensional cartesian geometry. Thermohydraulic feedbacks can be accounted for. The Effective Diffusion Homogenization method is used for generating the homogenized cross sections.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The complexity of the problem is selected by the user, depending on the capacity of his computer.
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6. TYPICAL RUNNING TIME

On Digital Alpha the approximate running time are as follows:
Test_1 : 1 second
Test_2 : 5 seconds
Test_3 : 5 minutes
Test_3a: 5 minutes
Test_4 : 15 seconds
Test_5 : 1 hour 30 minutes
Test_6 : 3 hours 35 minutes
Test_7 : 15 hours 10 minutes
Test_8 : 15 seconds
On 66 MHz PC-486 the complete test sequence takes approximately four days.
IAEA1226/03
The test cases included in this package were executed at the NEA Data Bank on a DEC VAX-6000-510 computer. The following CPU times were required:

  Test 1  ->                       4 sec
  Test 2  ->                      14 sec
  Test 3  ->              20 min  06 sec
  Test 3a ->              40 min  51 sec
  Test 4  ->               1 min  59 sec
  Test 5  ->         4 h  29 min  52 sec
  Test 6  ->         7 h  01 min  38 sec
  Test 7  -> 1 day  21 h  44 min  02 sec
  Test 8  ->                      44 sec
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7. UNUSUAL FEATURES OF THE PROGRAM

The package provides the calculational as well as data maintenance modules. Once the system is set up, it is relatively easy to use for design calculations of subsequent cycles of operation for a particular power plant.
Reflective quadrant core symmetry, cyclic quadrant symmetry and octant symmetry options are available.
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8. RELATED AND AUXILIARY PROGRAMS

- WIMS-D/4 Lattice code,
- GNOMER   Neutron diffusion code
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9. STATUS
Package ID Status date Status
IAEA1226/03 23-MAY-1996 Tested at NEADB
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10. REFERENCES

- A. Trkov:
  GNOMER - Multigroup 3-Dimensional Neutron Diffusion Nodal Code
  with Thermohydraulic Feedbacks,
  Institute Jozef Stefan, Ljubljana, Slovenia,
  IJS-DP-6688 (March 1993)
- A. Trkov and M. Ravnik:
  CORD-2 Package for PWR Nuclear Core Design Calculations,
  Proceedings of the International Conference on Reactor Physics
  and Reactor Computations, Tel-Aviv (Jan. 23-26, 1994)
- A. Trkov and M. Ravnik:
  Effective diffusion Homogenization of Cross Sections for PWR Core
  Calculations, Nucl.Sci.Eng. Vol.116, No.2, pp.86-95 (Feb. 94)
IAEA1226/03, included references:
- A. Trkov, N. Zeleznik:
  The Nuclear Core Design Manual, FASLIB - Fuel Assembly Library
  Management
  IJS-DP-6144 Rev. 2 (March 21, 1994)
- A. Trkov:
  The Nuclear Core Design Manual, Core Diffusion Cross Section
  Preparation
  IJS-DP-6173 Rev. 1 (March 21, 1994)
- M. Ravnik and al.:
  CORD-2 Core Design System for PWR Type Reactors
  IJS-DP-6174 Rev. 1 (July 28, 1994)
- A. Trkov:
  The Nuclear Core Design Manual, CORLIB Library Specifications
  IJS-DP-6175 Rev. 2 (March 21, 1994)
- A. Trkov:
  CORD-2 Package Users'Guide
  IJS-DP-6948 (August 3, 1994)
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11. MACHINE REQUIREMENTS

IBM/PC with 640K main memory and about 30 MB  disk space, VAX/VMS or OpenVMS with about 40 000 blocks of disk space.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA1226/03 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
On a PC: PC-DOS Ver.5; on VAX: VMS, OpenVMS
IAEA1226/03
The test runs were performed at the NEA Data Bank on a  DEC VAX-6000-510 computer running under VMS V.6.1. The source codes  were compiled with the VAX FORTRAN compiler version 6.2-108.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

To
execute a sequence of codes as necessary for a realistic calculation, the use of job control language is inevitable, but it has been kept to a minimum for better code portability. Appropriate  procedures are provided for VAX/VMS and PC/DOS systems. These may serve as examples to the user, to make adjustments for his specific  requirements or implementation on other operating systems.
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15. NAME AND ESTABLISHMENT OF AUTHORS

Andrej Trkov
"Jozef Stefan" Institute
Reactor Physics Division
61111 Ljubljana, Jamova 39, PO. BOX 100
SLOVENIA
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16. MATERIAL AVAILABLE
IAEA1226/03
File name File description Records
IAEA1226_03.001 Information file 272
IAEA1226_03.002 Installation and test procedure 206
IAEA1226_03.003 Utility programs main Fortran source 17866
IAEA1226_03.004 Common routines Fortran source 4257
IAEA1226_03.005 Additional routines Fortran source 10517
IAEA1226_03.006 Additional PC-specific codes Fortran source 864
IAEA1226_03.007 Source code file maintenance (Fortran) 155
IAEA1226_03.008 Source code file maintenance (Fortran) 69
IAEA1226_03.009 Rename files from distribution media VAX/VMS 101
IAEA1226_03.010 Moves file to their target directories (VMS) 80
IAEA1226_03.011 Installation procedure for VAX/VMS 60
IAEA1226_03.012 Installation procedure for VAX/OpenVMS 63
IAEA1226_03.013 Installation procedure for PC 68
IAEA1226_03.014 Compiling and linking procedure for PC 5
IAEA1226_03.015 Utility module execution procedure for PC 19
IAEA1226_03.016 CORD-2 settings on PC 14
IAEA1226_03.017 Core cross section preparation procedure PC 51
IAEA1226_03.018 Cross section editing on PC-1 reg to 10 reg 21
IAEA1226_03.019 Cross section editing on PC-1 reg to 24 reg 21
IAEA1226_03.020 Aux.proc. for submitting jobs into a batch q 42
IAEA1226_03.021 Default settings for Almaraz-II calculations 5
IAEA1226_03.022 Not used 5
IAEA1226_03.023 CORD-2 settings on VAX (modiy for install) 15
IAEA1226_03.024 Auxiliary batch proc. for checking CPU time 19
IAEA1226_03.025 Procedure for clearing unnecessary files 6
IAEA1226_03.026 Copy FASlib files to the Master lib. direc. 21
IAEA1226_03.027 Sample procedure for FASlib files editing 86
IAEA1226_03.028 Core cross section preparation proc. for VAX 230
IAEA1226_03.029 Reflector cross section prepa. proc. for VAX 37
IAEA1226_03.030 Run WIMS-D/4 with local WD4IJS1 library 21
IAEA1226_03.031 Execute WIMS runs for all inputs from WICORD 130
IAEA1226_03.032 SAMPLE Finish procedure for burnup calculat. 71
IAEA1226_03.033 not used 22
IAEA1226_03.034 Sample procedure for generating ISOLIB libr. 206
IAEA1226_03.035 Cross section edit on VAX - 1 reg to 10 reg 20
IAEA1226_03.036 Cross section edit on VAX - 1 reg to 24 reg 20
IAEA1226_03.037 Cross section edit on VAX -10 reg to 24 reg 38
IAEA1226_03.038 not used 99
IAEA1226_03.039 not used 5
IAEA1226_03.040 Procedure to execute all test cases on VAX 158
IAEA1226_03.041 Procedure to execute all test cases on PC 124
IAEA1226_03.042 WIMLIB library summary file 320
IAEA1226_03.043 DIMLIB library file for Almaraz-II 164
IAEA1226_03.044 FASLIB merged library file 943
IAEA1226_03.045 GNOMER input for reactivity coef. calc. 156
IAEA1226_03.046 GNOMER input for control rod worth calcula. 1034
IAEA1226_03.047 GNOMER input for Almaraz core octant at HZP 69
IAEA1226_03.048 GNOMER input for Almaraz core octant at HFP 79
IAEA1226_03.049 GNOMER input for Almaraz core quadrant HZP 67
IAEA1226_03.050 GNOMER input for Almaraz core quadrant HFP 75
IAEA1226_03.051 Proc. for generating the ISOLIB library VAX 216
IAEA1226_03.052 Proc. for generating the ISOLIB library PC 72
IAEA1226_03.053 Generic reactivity coefficient library 45
IAEA1226_03.054 Measured power distribution 10
IAEA1226_03.055 CORlib file with burnup to EOC (measured) 343
IAEA1226_03.056 Loading pattern CORlib for Almaraz II cycle1 63
IAEA1226_03.057 Design CORlib file at BOC 220
IAEA1226_03.058 Design CORlib file with burnup to EOC 4583
IAEA1226_03.059 Procedure to generate the design CORlib(VAX) 14
IAEA1226_03.060 Procedure to generate the design CORlib (PC) 9
IAEA1226_03.061 Procedure for updating the FASlib files VAX 33
IAEA1226_03.062 Procedure for updating the FASlib files PC 31
IAEA1226_03.063 Procedure calculation reactivity coeff. VAX 46
IAEA1226_03.064 Procedure calculation reactivity coeff. PC 38
IAEA1226_03.065 Input file calculation reactivity coeff. VAX 41
IAEA1226_03.066 Input file calculation reactivity coeff. PCX 41
IAEA1226_03.067 Ref CORlib file on K-eff for reac coeff 111
IAEA1226_03.068 Main input for power distr calc at HZP (VAX) 150
IAEA1226_03.069 Main input for power distr calc at HZP (PC) 150
IAEA1226_03.070 Main input for control rod worth calc. (VAX) 9
IAEA1226_03.071 Main input for control rod worth calc. (PC) 9
IAEA1226_03.072 Proc for power distrib calculation HZP (VAX) 22
IAEA1226_03.073 Proc for power distrib calculation HZP (PC) 40
IAEA1226_03.074 Proc for control rod worth calculation (PC) 9
IAEA1226_03.075 Proc for control rod worth calculation (VAX) 12
IAEA1226_03.076 Sample output from power distribution calc. 75
IAEA1226_03.077 Sample CORlib output from power distr.calc. 58
IAEA1226_03.078 Sample CORlib output from CR worth calcul. 107
IAEA1226_03.079 Sample unrodded core cond. specif. file 260
IAEA1226_03.080 Sample unrodded core cross sections file 520
IAEA1226_03.081 Sample rodded core conditions specif file 90
IAEA1226_03.082 Sample rodded cross sections file 180
IAEA1226_03.083 Sample reflector conditions specific. file 3
IAEA1226_03.084 Sample reflector cross sections file 6
IAEA1226_03.085 Main input for power distrib calc HFP (VAX) 39
IAEA1226_03.086 Main input for power distrib calc HFP (PC) 40
IAEA1226_03.087 Proc for power ditribution calc. HFP (VAX) 10
IAEA1226_03.088 Proc for power ditribution calc. HFP (PC) 12
IAEA1226_03.089 Sample output power distribution calculation 62
IAEA1226_03.090 Sample CORlib output power distrib. calc. 1
IAEA1226_03.091 Proc for power distrib calc during burnupVAX 37
IAEA1226_03.092 Proc for power distrib calc during burnup PC 30
IAEA1226_03.093 Input for power distr calc during burnup VAX 41
IAEA1226_03.094 Input for power distr calc during burnup PC 41
IAEA1226_03.095 DOS file-names 94
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17. CATEGORIES
  • C. Static Design Studies
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: coarse mesh, cross sections, diffusion equations, multigroup, power distribution, pressurized water reactor, three-dimensional.