last modified: 18-APR-1996 | catalog | categories | new | search |

IAEA1271 GNOMER.

GNOMER, Core Power Distribution by 1-D, 2-D, 3-D MultiGroup Neutron Diffusion

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1. NAME OR DESIGNATION OF PROGRAM:  GNOMER.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
GNOMER IAEA1271/03 Tested 18-APR-1996

Machines used:

Package ID Orig. computer Test computer
IAEA1271/03 VAX generic,IBM PC PC Windows,VAX generic
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3. DESCRIPTION OF PROGRAM OR FUNCTION

GNOMER is a program which solves the multigroup neutron diffusion equation in 1D, 2D and 3D cartesian geometry. The program is designed to calculate the global  core power distributions (with thermohydraulic feedbacks), as well as power distributions and homogenized cross sections over a fuel assembly.
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4. METHOD OF SOLUTION

It uses the highly efficient Green's function nodal method.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME

Few seconds on IBM/PC-AT-486 compatible computer for 2D geometry. Three minutes on IBM/PC-AT-486 compatible computer for 3D geometry.
IAEA1271/03
NEA-DB ran the test cases included in this package on both a VAXStation 3100 M38 and a Pentium 75MHz PC. The following execution times were found:
Tests           VAX         Lahey Fortran
----           ---         -------------
  T1        01.94 sec         00.28 sec
  T2        87.39 sec         23.62 sec
  T3       150.67 sec         34.50 sec
  T4       725.51 sec        106.23 sec
  T5        50.09 sec         17.96 sec
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7. UNUSUAL FEATURES OF THE PROGRAM

A simple thermohydraulic module to calculate temperature distribution is included. The Reactivity Coefficient method is applied for small corrections to cross sections when core conditions differ from nominal (at which the cross sections have been tabulated) due to thermohydraulic feedbacks. -Cyclic quadrant symmetry and octant symmetry options are available.
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8. RELATED AND AUXILIARY PROGRAMS:  None.
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9. STATUS
Package ID Status date Status
IAEA1271/03 18-APR-1996 Tested at NEADB
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10. REFERENCES

- H. Finnemann, F. Benewits, M.R. Wagner:
Interface Current Techniques for Multi-Dimensional Calculations
Atomkernenergie, Bd. 30, Lfg.2 (1977).
- A. Trkov, M. Najzer, L. Skerget:
A Variant of the Green's Function Method for Neutron Diffusion
Jou.Nucl.Sci.Tech., Vol. 27, No. 8, pp. 766-777 (Aug. 1990).
- National Energy Software Center:
Benchmark Problem Book, ANL-7416, Suppl. 1,2,3 (1985).
- A. Trkov and M. Ravnik:
Effective Diffusion Homogenization of Cross Sections for PWR Core
Calculations, Nucl.Sci.Eng., Vol.116, pp.86-95, February 1994.
IAEA1271/03, included references:
- A. Trkov:
  GNOMER - Multigroup 3-Dimensional Neutron Diffusion Nodal Code
  with Thermohydraulic Feedbacks
  IJS-DP-6688 Rev. 2 (July 29, 1994).
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11. MACHINE REQUIREMENTS:  IBM/PC with 640K main memory.
IAEA1271/03
The program was installed by NEA-DB on both a VAXStation 3100 M38 and a Brett Pentium-75MHz PC with 16 MBytes of RAM.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA1271/03 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  PC-DOS version 5
(PC); VMS, OpenVMS (VAX).
IAEA1271/03
The program was installed and executed by NEA-DB on: - VAXstation running under VMS 6.1 with the VAX FORTRAN compiler version 6.2; - on PC/P75 under Windows 95 and using the Lahey FORTRAN version 5.20. compiler.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:  None.
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15. NAME AND ESTABLISHMENT OF AUTHORS

          Andrej Trkov
     "Josef Stefan" Institute
      Reactor Physics Division
     61111 Ljubljana, Jamova 39, P.O. Box 100
     Slovenia
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16. MATERIAL AVAILABLE
IAEA1271/03
File name File description Records
IAEA1271_03.001 Information file 168
IAEA1271_03.002 GNOMER Fortran source file 7361
IAEA1271_03.003 Code-conversion program 155
IAEA1271_03.004 Source code splitting program 69
IAEA1271_03.005 Comp & link procedure for PC (Microsoft) 60
IAEA1271_03.006 Comp & link procedure for PC (NDP) 30
IAEA1271_03.007 Comp & link procedure for PC (Lahey) 35
IAEA1271_03.008 Installation command procedure for VAX 71
IAEA1271_03.009 Link file for PC (Microsoft FORTRAN) 7
IAEA1271_03.010 Executable code for PC (Lahey Fortran) 0
IAEA1271_03.011 Command procedure for test cases in PC 37
IAEA1271_03.012 Command procedure for test cases on VAX 47
IAEA1271_03.013 Command procedure for routing tests to batch 12
IAEA1271_03.014 Information provided by the author 202
IAEA1271_03.015 Lahey error messages 0
IAEA1271_03.016 CCCCCCCCCCCn difusion 126
IAEA1271_03.017 GNOMEX installation using MS Fortran 72
IAEA1271_03.018 Benchmark reference solution (test case-1) 13
IAEA1271_03.019 Test case-1 input (IAEA-2D benchmark) 37
IAEA1271_03.020 Cross sections for the IAEA-2D benchmark 8
IAEA1271_03.021 Test case-1 output on VAX 60
IAEA1271_03.022 Test case-1 output on PC (Lahey) 70
IAEA1271_03.023 Test case-2 input (IAEA-3D benchmark) 83
IAEA1271_03.024 Benchmark reference solution (test case-2) 175
IAEA1271_03.025 Test case-2 output on VAX 50
IAEA1271_03.026 Test case-2 output on PC (Lahey) 50
IAEA1271_03.027 BPR cell cross sections of assembly G08 20
IAEA1271_03.028 Control rod cell X sections of assembly G08 20
IAEA1271_03.029 Control rod cell X sections of assembly G08 20
IAEA1271_03.030 Fuel cell X sections of assembly G08 20
IAEA1271_03.031 Fuel cell X sections of assembly G08 20
IAEA1271_03.032 Fuel cell X sections of assembly G08 20
IAEA1271_03.033 Water cell X sections of assembly G08 20
IAEA1271_03.034 Water cell X sections of assembly G08 20
IAEA1271_03.035 Water cell X sections of assembly G08 20
IAEA1271_03.036 Test case-3 input (Assembly homogenization) 120
IAEA1271_03.037 Homogenized assembly cross sections (output) 6
IAEA1271_03.038 Test case-3 output on VAX 33
IAEA1271_03.039 Test case-3 output on PC (Lahey) 33
IAEA1271_03.040 Core cond. at which core X sect. are defined 370
IAEA1271_03.041 Unrodded core cross sections 740
IAEA1271_03.042 Core cond. at which control rod X sec def. 110
IAEA1271_03.043 Control rod cross sections 220
IAEA1271_03.044 Reflector cross sections 6
IAEA1271_03.045 Reactivity coefficient library 44
IAEA1271_03.046 Test case-4 input (PWR core with feddbacks) 20
IAEA1271_03.047 Auxiliary input reflective quadrant symmetry 122
IAEA1271_03.048 Auxiliary input cycling quadrant symmetry 150
IAEA1271_03.049 Output in Corlib format (reflective) 94
IAEA1271_03.050 Output in Corlib format (cyclic) 94
IAEA1271_03.051 Measured data for same configuration (ref) 11
IAEA1271_03.052 Test case-4 output on VAX 146
IAEA1271_03.053 Test case-4 output on PC (Lahey) 146
IAEA1271_03.054 Test case-5 input (Henry-Worley het. bench.) 46
IAEA1271_03.055 Reference solution by Koebke 29
IAEA1271_03.056 Output in CORlib format 5
IAEA1271_03.057 Test case-5 output on VAX 19
IAEA1271_03.058 Test case-5 output on PC (Lahey) 19
IAEA1271_03.059 DOS file-names 58
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17. CATEGORIES
  • C. Static Design Studies

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