last modified: 18-AUG-1995 | catalog | categories | new | search |

CCC-0603 FPZD.

FPZD, Reactor Burnup by MultiGroup Neutron Diffusion

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1. NAME OR DESIGNATION OF PROGRAM:  FPZD (Code System for Multigroup
Neutron Diffusion/Depletion Calculations).
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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
FPZD CCC-0603/01 Tested 18-AUG-1995

Machines used:

Package ID Orig. computer Test computer
CCC-0603/01 IBM PC PC Pentium 75
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3. DESCRIPTION OF PROGRAM OR FUNCTION

FPZD calculates the spatial power and neutron flux distributions of a nuclear reactor along with its effective multiplication factor and time-dependent material compositions.
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4. METHOD OF SOLUTION

The depletion subroutines permit a very generalized nuclide depletion scheme to be used in which the materials may be distributed into a number of burnup subregions each containing a different atom density set. Depletion of the nuclides is calculated separately for each burnup subregion assuming exposure to the average flux of the spatial region. The macroscopic properties of a spatial region are calculated by giving the appropriate volume fraction weighting factors to the cross sections  of the burnup subregions.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  Non noted.
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6. TYPICAL RUNNING TIME

On a 20 MHZ PC 386 with a math co-processor,  the following times were noted: FPZDIN.INI took 45 minutes; FPZDIN.KIC took 25 minutes; FPZDIN.IC took 35 minutes; FPZDIN.KRL took 45 minutes, FPZDIN.RL took 40 minutes.
CCC-0603/01
The program FPZD was executed at the NEA-DB on a PC Brett (Pentium processor 75 MHz) under MS-DOS 6.2. The times required to run the five test cases are displayed in the following table.
       Test case      Input     Elapsed time
           #        filename
      ---------------------------------------
           1       FPZDIN.INI       4m44s
           2       FPZDIN.KIC       4m47s
           3       FPZDIN.IC        6m20s
           4       FPZDIN.KRL       8m43s
           5       FPZDIN.RL        7m54s
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

Two auxiliary programs are provided:
- The program CONVERT, to convert cross-sections data files in ANISN, INEL or ISOTXS formats into a format usable by FPZD.
- The plotting program PLOTFPZD, to display the output results produced in a given FPZD run. This program is written in C language.
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9. STATUS
Package ID Status date Status
CCC-0603/01 18-AUG-1995 Tested at NEADB
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10. REFERENCES:
CCC-0603/01, included references:
- B. Emmrich:
  A One-Dimensional Multigroup Neutron Diffusion/Depletion Code for
  Performing Control and Fuel Loading Searches and for Determining
  the Fuel and Poison Distributions Required to Achieve Burnup
  Independent Power Distributions with Optional Thermal-Fluid
  Feedback
  NASA Informal Document, Marshall Flight Center, Huntsville,
  Alabama (June 1992).
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11. MACHINE REQUIREMENTS

FPZD runs on the PC 386 or PC 486 under the DOS 5.0 operating system; a math co-processor is required.
CCC-0603/01
Two different make files are provided to compile the source files and create the FPZD executable: one uses the NMAKE Program Maintenance Utility (requires the Microsoft Fortran Version  5.10 or higher) and the other to be used with the MAKE utility program (Microsoft Fortran Version 5.01). MEMORY REQUIREMENTS: More  than 472 Kbyte of conventional memory available are required to execute the NMAKE Utility on the file MAKEFILE. DISKSPACE REQUIREMENTS: The filesize of the executable FPZD.EXE is 450 Kbyte.  The diskspace required by the output files produced during the execution of the five sample problems is 7.0 Mbyte, distributed as follows: 0.9 Mbyte (problem #1), 0.8 Mbyte (problem #2), 1.7 Mbyte (problem #3), 2.0 Mbyte (problem #4) and 1.6 Mbyte (problem #5). The diskspace required by the 62 source files is 311 Kbyte. The diskspace occupied by the corresponding 62 object files after compilation is 582 Kbyte.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
CCC-0603/01 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

The code was written in FORTRAN 77 and was tested using the Microsoft Version 5.01 compiler.
CCC-0603/01
FPZD was run under MS-DOS 6.2 on a PC Brett (Pentium processor 75 MHz). The FORTRAN source files were compiled using the  Microsoft FORTRAN compiler and linker (Version 5.10). The Microsoft  NMAKE Program Maintenance Utility Version 1.13 was used in order to  compile the source files and build the FPZD executable. A make file  to be used with the Borland MAKE Utility (compatible with the Microsoft Fortran Version 5.01) is also provided.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by: Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.

Developed by:   Marshall Space Flight Center
                NASA
                Huntsville, Alabama, U.S.A.
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16. MATERIAL AVAILABLE
CCC-0603/01
File name File description Records
CCC0603_01.001 Information file of program FPZD 726
CCC0603_01.002 FPZD document in WordPerfect 5.1 format 0
CCC0603_01.003 WordPerfect 5.1 Macro 0
CCC0603_01.004 Makefile for MicroSoft compiler Version 5.10 22
CCC0603_01.005 Makefile for MicroSoft compiler Version 5.01 195
CCC0603_01.006 Batch file to create the executabel FPZD.EXE 39
CCC0603_01.007 Batch file to compile FORTRAN source files 9
CCC0603_01.008 Link file to create the executable FPZD.EXE 31
CCC0603_01.009 Source file # 1 56
CCC0603_01.010 Source file # 2 67
CCC0603_01.011 Source file # 3 191
CCC0603_01.012 Source file # 4 55
CCC0603_01.013 Source file # 5 153
CCC0603_01.014 Source file # 6 34
CCC0603_01.015 Source file # 7 322
CCC0603_01.016 Source file # 8 84
CCC0603_01.017 Source file # 9 29
CCC0603_01.018 Source file # 10 102
CCC0603_01.019 Source file # 11 381
CCC0603_01.020 Source file # 12 65
CCC0603_01.021 Source file # 13 73
CCC0603_01.022 Source file # 14 245
CCC0603_01.023 Source file # 15 62
CCC0603_01.024 Source file # 16 14
CCC0603_01.025 Source file # 17 89
CCC0603_01.026 Source file # 18 161
CCC0603_01.027 Source file # 19 140
CCC0603_01.028 Source file # 20 14
CCC0603_01.029 Source file # 21 205
CCC0603_01.030 Source file # 22 792
CCC0603_01.031 Source file # 23 67
CCC0603_01.032 Source file # 24 568
CCC0603_01.033 Source file # 25 155
CCC0603_01.034 Source file # 26 42
CCC0603_01.035 Source file # 27 24
CCC0603_01.036 Source file # 28 52
CCC0603_01.037 Source file # 29 657
CCC0603_01.038 Source file # 30 9
CCC0603_01.039 Source file # 31 51
CCC0603_01.040 Source file # 32 30
CCC0603_01.041 Source file # 33 81
CCC0603_01.042 Source file # 34 442
CCC0603_01.043 Source file # 35 151
CCC0603_01.044 Source file # 36 223
CCC0603_01.045 Source file # 37 81
CCC0603_01.046 Source file # 38 93
CCC0603_01.047 Source file # 39 203
CCC0603_01.048 Source file # 40 75
CCC0603_01.049 Source file # 41 48
CCC0603_01.050 Source file # 42 132
CCC0603_01.051 Source file # 43 129
CCC0603_01.052 Source file # 44 34
CCC0603_01.053 Source file # 45 145
CCC0603_01.054 Source file # 46 35
CCC0603_01.055 Source file # 47 184
CCC0603_01.056 Source file # 48 21
CCC0603_01.057 Source file # 49 111
CCC0603_01.058 Source file # 50 18
CCC0603_01.059 Source file # 51 65
CCC0603_01.060 Source file # 52 213
CCC0603_01.061 Source file # 53 23
CCC0603_01.062 Source file # 54 11
CCC0603_01.063 Source file # 55 61
CCC0603_01.064 Source file # 56 75
CCC0603_01.065 Source file # 57 36
CCC0603_01.066 Source file # 58 109
CCC0603_01.067 Source file # 59 51
CCC0603_01.068 Source file # 60 31
CCC0603_01.069 Source file # 61 82
CCC0603_01.070 Include file # 1 (COMMON /FIXFLT/) 18
CCC0603_01.071 Include file # 2 (definition of arrays) 53
CCC0603_01.072 FPZD executable (MicroSoft Version 5.10) 0
CCC0603_01.073 FPZD executable (MicroSoft Version 5.01) 0
CCC0603_01.074 Input file for test case # 1 157
CCC0603_01.075 Input file for test case # 2 151
CCC0603_01.076 Input file for test case # 3 162
CCC0603_01.077 Input file for test case # 4 233
CCC0603_01.078 Input file for test case # 5 289
CCC0603_01.079 Atom density input file 160
CCC0603_01.080 Table of delta(k-infinity) (from case #2) 40
CCC0603_01.081 Table of delta(k-infinity) (from case #4) 40
CCC0603_01.082 Microscopic neutron cross-sections library 509
CCC0603_01.083 Output file produced from test case # 1 15915
CCC0603_01.084 Output file produced from test case # 2 20867
CCC0603_01.085 Output file produced from test case # 3 31433
CCC0603_01.086 Output file produced from test case # 4 39617
CCC0603_01.087 Output file produced from test case # 5 26727
CCC0603_01.088 README File of auxiliary program CONVERT 11
CCC0603_01.089 FORTRAN-77 source file of program CONVERT 451
CCC0603_01.090 Executable file of program CONVERT 0
CCC0603_01.091 Sample input file (x-sections, ANISN format) 10
CCC0603_01.092 Sample input file (x-sections, INEL format) 7
CCC0603_01.093 Sample input file (x-sections, ISOTXS formt) 7
CCC0603_01.094 Cross-sections data file in ANISN format 106
CCC0603_01.095 Cross-sections data file in INEL format 158
CCC0603_01.096 Cross-sections data file in ISOTXS format 128
CCC0603_01.097 Output file porduced by program CONVERT 67
CCC0603_01.098 C-language source file # 1 35
CCC0603_01.099 C-language source file # 2 190
CCC0603_01.100 C-language source file # 3 32
CCC0603_01.101 C-language source file # 4 458
CCC0603_01.102 C-language source file # 5 631
CCC0603_01.103 C-language source file # 6 57
CCC0603_01.104 C-language source file # 7 244
CCC0603_01.105 C-language source file # 8 53
CCC0603_01.106 Include file 14
CCC0603_01.107 Auxiliary file 9
CCC0603_01.108 Executable file of program PLOTFPZD 0
CCC0603_01.109 Plot file # 1 (to be displayed by PLOTFPZD) 0
CCC0603_01.110 Plot file # 2 (to be displayed by PLOTFPZD) 0
CCC0603_01.111 DOS file-names 110
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17. CATEGORIES
  • C. Static Design Studies
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: burnup, depletion, multiplication factors, neutron flux.