IAEA0871 VPI-NECM.

1. NAME OR DESIGNATION OF PROGRAM:  VPI-NECM. Nuclear Engineering Computer Modules for in-core fuel management analysis.

3. DESCRIPTION OF PROBLEM OR FUNCTION

The VPI MODULES consist of 6 independent programs designed to calculate:
module FARCON - neutron slowing down and epithermal group constants, module SLOCON - thermal neutron spectrum and group constants,
module DISFAC - slow neutron disadvantage factors,
module ODOG - solution of a one group neutron diffusion equation,
module ODMUG - three group critically problem,
module FUELBURN - fuel burnup in slow neutron fission reactors.

4. METHOD OF SOLUTION

Module FARCON solves the diffusion equation for a homogeneous medium composed of N isotopes, in 33 groups in fast and resonance energy region. The solution in the thermal energy region carried out by module SLOCON is based on the Wigner-Wilkins approximation and applies the Runge-Kutta method. The burnup cal- culations are carried out in 3 energy groups. Only Xe-135 and Sm-149 are treated directly. All the other fission products are represented by 2 pseudo isotopes. Module ODOG solves the finite difference diffusion equation by a direct method. Module ODMUG uses the Chebyshev acceleration of outer iterations. It gives a possibility to calculate a critical boron concentration.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

It is assumed that the elementary reactor cell consists of the fuel rod surrounded by water. The library data are limited to isotopes typical for water power reactors. The reactor can be treated in one dimension only, i. e. as a slab, sphere or cylinder with one-dimensional symmetry.

6. TYPICAL RUNNING TIME

The execution time of one module varies from  0.051 seconds to 1.479 seconds.

NEA-DB executed the test case included in the package on CDC CYBER 740. The following CPU times were required:
                  FARCON test case:    5 seconds
                  SLOCON               3
                  DISFAC               1
                  ODOG                 2
                  ODMUG                5
                  FUELBURN             2

NEA-DB executed the test case included in the package on a VAX-11/780. The following CPU times were required:
                  FARCON test case:    5 seconds
                  SLOCON               5
                  DISFAC               3
                  ODOG                 4
                  ODMUG                5
                  FUELBURN            24

7. UNUSUAL FEATURES OF THE PROGRAM

The program package is designed for educational purposes. It is based on simple physical models and  numerical techniques. This way very short computing times and low computer requirements have been achieved. At the same time the package consists of the basic modules necessary for modern in-core fuel management analysis and its usage delivers the student proper ideas about the in-core fuel management calculational process in realistic cases.

8. RELATED AND AUXILIARY PROGRAMS

The resonance data can be obtained  by module REP developed also at Virginia Polytechnic Institute and State University and not included into the present program package.

10. REFERENCES

- S.H. Levine,
  MODULE-5 "In-Core Management", Editer N.D. Eckhot Kansas State
  University, 1980.

- T. Kulikowska and B. Szczesna:
  The VPI Program Package, Preliminary Version (February 1984)
- T. Kulikowska:
  Report on work performed during the third year of the coordinated
  research programme on codes adaptable to small and medium size
  computers in developing countries for in-core fuel management
- T. Kulikowska et al.:
  Progress Report No. 5 July 1, 1983 - March 31, 1984
- T. Kulikowska and B. Szczesna:
  Remarks on VPI program package usage
- T. Kulikowska and B. Szczesna:
  Translation of VPI program package to the CDC computer
- H.A. Kurstedt, Jr.:
  Nuclear Safety Module, NSM-1, Reliability Analysis for Reactor
  Safety, VPI and SU, Blacksburg, Virginia.
- H.A. Kurstedt, Jr.:
  Nuclear Safety Module, NSM-2, Fission Product Release, VPI and SU,
  Blacksburg, Virginia.
- R.L. Whitelaw:
  Nuclear Power Plant Module, NPP-1, Nuclear Power Cost Analysis,
  VPI and SU, Blacksburg, Virginia.
- M.C. Edlund:
  Fuel Management Module, FM-1, Fuel Burnup in Slow Neutron Fission
  Reactors, VPI and SU, Blacksburg, Virginia.
- M.C. Edlund:
  Fuel Management Module, FM-2, Fast Reactor Fuel Cycle Program,
  VPI and SU, Blacksburg, Virginia.
- G.H. Beyer:
  Fuel Management Module, FM-3, Feed Material and Separation Work
  Requirements for Enriching Uranium by Gaseous Diffusion, VPI and
  SU, Blacksburg, Virginia.
- R.J. Onega:
  Reactor Dynamics Module, RD-1, The Reactor Kinetics Equations, VPI
  and SU, Blacksburg, Virginia.
- R.J. Onega:
  Reactor Dynamics Module, RD-2, Reactor Kinetics with Feedback, VPI
  and SU, Blacksburg, Virginia.
- M.C. Edlund:
  Introduction to Reactor Statics Modules,
  RS-1, VPI and SU, Blacksburg, Virginia.
- R.J. Onega:
  Reactor Statics Module, RS-2, The Numerical Solution of the One
  Group Neutron Diffusion Equation, VPI & SU, Blacksburg, Virginia.
- R.L. Bowden, M.C. Edlund,
  Reactor Statics Module, RS-3, Neutron Slowing Down and Epithermal
  Group Constants, VPI and SU, Blacksburg, Virginia.
  P.F. Zweifel:
  Reactor Statics Module, RS-4, Resonance Absorption, VPI and SU,
  Blacksburg, Virginia.
  M.C. Edlund:
  Reactor Statics Module, RS-5, Multigroup Constants for Fast
  Breeder Reactors, VPI and SU, Blacksburg, Virginia.
  R.J. Onega, M.C. Edlund and L. Mync:
  Reactor Statics Module, RS-6, Slow Neutron Disadvantage Factors
- R.J. Onega:
  Reactor Statics Module, RS-7, Thermal Neutron Spectra and Thermal
  Group Constants for Light Water Reactors, VPI and SU, Blacksburg,
  Virginia.
- J.R. Thomas:
  Reactor Statics Module, RS-8, Three Group Criticality Program,
  VPI and SU, Blacksburg, Virginia.
- J.B. Dee (Project Officer):
  In-Core Fuel Management Programs for Nuclear Power Reactors
  IAEA-TECDOC-314  (October 1984)
- G.H. Beyer:
Fuel Management Module, FM-3 Feed Material and Separation Work
Requirements for Enriching Uranium by Gaseous Diffusion
- T. Kulikowska and B. Szczesna:
  The VPI Program Package, Preliminary Version (February 1984)
- T. Kulikowska:
  Report on work performed during the third year of the coordinated
  research programme on codes adaptable to small and medium size
  computers in developing countries for in-core fuel management
- T. Kulikowska et al.:
  Progress Report No. 5 July 1, 1983 - March 31, 1984
- T. Kulikowska and B. Szczesna:
  Remarks on VPI program package usage
- H.A. Kurstedt, Jr.:
  Nuclear Safety Module, NSM-1, Reliability Analysis for Reactor
  Safety, VPI and SU, Blacksburg, Virginia.
- H.A. Kurstedt, Jr.:
  Nuclear Safety Module, NSM-2, Fission Product Release, VPI and SU,
  Blacksburg, Virginia.
- R.L. Whitelaw:
  Nuclear Power Plant Module, NPP-1, Nuclear Power Cost Analysis,
  VPI and SU, Blacksburg, Virginia.
- M.C. Edlund:
  Fuel Management Module, FM-1, Fuel Burnup in Slow Neutron Fission
  Reactors, VPI and SU, Blacksburg, Virginia.
- M.C. Edlund:
  Fuel Management Module, FM-2, Fast Reactor Fuel Cycle Program,
  VPI and SU, Blacksburg, Virginia.
- G.H. Beyer:
  Fuel Management Module, FM-3, Feed Material and Separation Work
  Requirements for Enriching Uranium by Gaseous Diffusion, VPI and
  SU, Blacksburg, Virginia.
- R.J. Onega:
  Reactor Dynamics Module, RD-1, The Reactor Kinetics Equations, VPI
  and SU, Blacksburg, Virginia.
- R.J. Onega:
  Reactor Dynamics Module, RD-2, Reactor Kinetics with Feedback, VPI
  and SU, Blacksburg, Virginia.
- M.C. Edlund:
  Introduction to Reactor Statics Modules,
  RS-1, VPI and SU, Blacksburg, Virginia.
- R.J. Onega:
  Reactor Statics Module, RS-2, The Numerical Solution of the One
  Group Neutron Diffusion Equation, VPI & SU, Blacksburg, Virginia.
- R.L. Bowden, M.C. Edlund,
  Reactor Statics Module, RS-3, Neutron Slowing Down and Epithermal
  Group Constants, VPI and SU, Blacksburg, Virginia.
  P.F. Zweifel:
  Reactor Statics Module, RS-4, Resonance Absorption, VPI and SU,
  Blacksburg, Virginia.
  M.C. Edlund:
  Reactor Statics Module, RS-5, Multigroup Constants for Fast
  Breeder Reactors, VPI and SU, Blacksburg, Virginia.
  R.J. Onega, M.C. Edlund and L. Mync:
  Reactor Statics Module, RS-6, Slow Neutron Disadvantage Factors
- R.J. Onega:
  Reactor Statics Module, RS-7, Thermal Neutron Spectra and Thermal
  Group Constants for Light Water Reactors, VPI and SU, Blacksburg,
  Virginia.
- J.R. Thomas:
  Reactor Statics Module, RS-8, Three Group Criticality Program,
  VPI and SU, Blacksburg, Virginia.
- J.B. Dee (Project Officer):
  In-Core Fuel Management Programs for Nuclear Power Reactors
  IAEA-TECDOC-314  (October 1984)
- G.H. Beyer:
Fuel Management Module, FM-3 Feed Material and Separation Work
Requirements for Enriching Uranium by Gaseous Diffusion
- T.Kulikowska and B.Szczesna ;
"Translation of VPI program package to the CDC computer"
- T. Kulikowska and B. Szczesna:
  The VPI Program Package, Preliminary Version (February 1984)
- T. Kulikowska:
  Report on work performed during the third year of the coordinated
  research programme on codes adaptable to small and medium size
  computers in developing countries for in-core fuel management
- T. Kulikowska et al.:
  Progress Report No. 5 July 1, 1983 - March 31, 1984
- T. Kulikowska and B. Szczesna:
  Remarks on VPI program package usage
- H.A. Kurstedt, Jr.:
  Nuclear Safety Module, NSM-1, Reliability Analysis for Reactor
  Safety, VPI and SU, Blacksburg, Virginia.
- H.A. Kurstedt, Jr.:
  Nuclear Safety Module, NSM-2, Fission Product Release, VPI and SU,
  Blacksburg, Virginia.
- R.L. Whitelaw:
  Nuclear Power Plant Module, NPP-1, Nuclear Power Cost Analysis,
  VPI and SU, Blacksburg, Virginia.
- M.C. Edlund:
  Fuel Management Module, FM-1, Fuel Burnup in Slow Neutron Fission
  Reactors, VPI and SU, Blacksburg, Virginia.
- M.C. Edlund:
  Fuel Management Module, FM-2, Fast Reactor Fuel Cycle Program,
  VPI and SU, Blacksburg, Virginia.
- G.H. Beyer:
  Fuel Management Module, FM-3, Feed Material and Separation Work
  Requirements for Enriching Uranium by Gaseous Diffusion, VPI and
  SU, Blacksburg, Virginia.
- R.J. Onega:
  Reactor Dynamics Module, RD-1, The Reactor Kinetics Equations, VPI
  and SU, Blacksburg, Virginia.
- R.J. Onega:
  Reactor Dynamics Module, RD-2, Reactor Kinetics with Feedback, VPI
  and SU, Blacksburg, Virginia.
- M.C. Edlund:
  Introduction to Reactor Statics Modules,
  RS-1, VPI and SU, Blacksburg, Virginia.
- R.J. Onega:
  Reactor Statics Module, RS-2, The Numerical Solution of the One
  Group Neutron Diffusion Equation, VPI & SU, Blacksburg, Virginia.
- R.L. Bowden, M.C. Edlund,
  Reactor Statics Module, RS-3, Neutron Slowing Down and Epithermal
  Group Constants, VPI and SU, Blacksburg, Virginia.
  P.F. Zweifel:
  Reactor Statics Module, RS-4, Resonance Absorption, VPI and SU,
  Blacksburg, Virginia.
  M.C. Edlund:
  Reactor Statics Module, RS-5, Multigroup Constants for Fast
  Breeder Reactors, VPI and SU, Blacksburg, Virginia.
  R.J. Onega, M.C. Edlund and L. Mync:
  Reactor Statics Module, RS-6, Slow Neutron Disadvantage Factors
- R.J. Onega:
  Reactor Statics Module, RS-7, Thermal Neutron Spectra and Thermal
  Group Constants for Light Water Reactors, VPI and SU, Blacksburg,
  Virginia.
- J.R. Thomas:
  Reactor Statics Module, RS-8, Three Group Criticality Program,
  VPI and SU, Blacksburg, Virginia.
- J.B. Dee (Project Officer):
  In-Core Fuel Management Programs for Nuclear Power Reactors
  IAEA-TECDOC-314  (October 1984)
- G.H. Beyer:
Fuel Management Module, FM-3 Feed Material and Separation Work
Requirements for Enriching Uranium by Gaseous Diffusion
T.Kulikowska and B.Szczesna;
"Translation of VPI program package to the CDC computer"

11. MACHINE REQUIREMENTS

The programs work entirely in the core memory of the computer. 60 000 words are needed to compile and run the modules.

Main storage requirements on CDC CYBER 740 for the different modules of the package are as follows:
FARCOM 27,124 (octal) words
SLOCON 21,621
DISFAC 14,225
ODOG 44,352
ODMUG 36,113
FUELBURN 17,023

Main storage requirements on VAX-11/780 for the different modules of the package are as follows:
FARCOM 27,504 bytes
SLOCON 16,896
DISFAC 4,608
ODOG 55,808
ODMUG 44,032
FUELBURN 13,312

The test cases were executed on a PC/80386 compatible desktop computer with a 80387 math coprocessor.

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  SCOPE 3.4. It can work also under NOS.

NOS 1.4-531 (CDC CYBER 740).

VMS-V3.4 (VAX-11/780).

MSDOS-4.01 with Microsoft FORTRAN 5.0 compiler.

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

15. NAME AND ESTABLISHMENT OF AUTHOR

PC version:
Ing. Jiri HONOMICHL
Manager
Power Machinery Plant
SKODA, Concern Enterprise
316 00 PLZEN, Czech Republic
  
CDC version:
Teresa Kulikowska, Barbara Szczesna
Institute of Atomic Energy
05-400 Otwock-Swierk, Poland
  
This code system has been included in the Coordinated Research Programme (CRP) on "Codes Adaptable to Small and Medium-Size Com- puters Available in Developing Countries for In-Core Fuel Manage- ment" of the International Atomic Energy Agency.
  
Virginia Polytechnic Institute
and
State University
Blacksburg, Virginia, U.S.A.

File name	File description	Records
IAEA0871_02.003	INFORMATION FILE	72
IAEA0871_02.004	FARCON SOURCE PROGRAM	340
IAEA0871_02.005	FARCON JCL TO RUN TEST CASE	19
IAEA0871_02.006	FARCON X-SEC LIBRARY (FORMATTED)	498
IAEA0871_02.007	AUX. PGM TO CONVERT FARCON X-SEC LIB	49
IAEA0871_02.008	FARCON TEST CASE INPUT DATA	7
IAEA0871_02.009	FARCON TEST CASE PRINTED OUTPUT	545
IAEA0871_02.010	SLOCON SOURCE PROGRAM	1093
IAEA0871_02.011	SLOCON JCL TO RUN TEST CASE	10
IAEA0871_02.012	SLOCON TEST CASE INPUT DATA	20
IAEA0871_02.013	SLOCON TEST CASE PRINTED OUTPUT	187
IAEA0871_02.014	DISFAC SOURCE PROGRAM	279
IAEA0871_02.015	DISFAC JCL TO RUN TEST CASE	10
IAEA0871_02.016	DISFAC TEST CASE INPUT DATA	1
IAEA0871_02.017	DISFAC TEST CASE PRINTED OUTPUT	53
IAEA0871_02.018	ODOG SOURCE PROGRAM	392
IAEA0871_02.019	ODOG JCL TO RUN TEST CASE	10
IAEA0871_02.020	ODOG TEST CASE INPUT DATA	7
IAEA0871_02.021	ODOG TEST CASE PRINTED OUTPUT	186
IAEA0871_02.022	ODMUG SOURCE PROGRAM	968
IAEA0871_02.023	ODMUG JCL TO RUN TEST CASE	10
IAEA0871_02.024	ODMUG TEST CASE INPUT DATA	15
IAEA0871_02.025	ODMOG TEST CASE PRINTED OUTPUT	580
IAEA0871_02.026	FUELBURN SOURCE PROGRAM	374
IAEA0871_02.027	FUELBURN JCL TO RUN TEST CASE	10
IAEA0871_02.028	FUELBURN TEST CASE INPUT DATA	4
IAEA0871_02.029	FUELBURN TEST CASE PRINTED OUTPUT	295

File name	File description	Records
IAEA0871_03.003	INFORMATION FILE	73
IAEA0871_03.004	FARCON SOURCE PROGRAM	348
IAEA0871_03.005	FARCON X-SEC LIBRARY (FORMATTED,EBCDIC)	498
IAEA0871_03.006	FARCON X-SEC LIB CONVERSION PROGRAM SOURCE	46
IAEA0871_03.007	FARCON TEST CASE INPUT DATA	7
IAEA0871_03.008	FARCON TEST CASE PRINTED OUTPUT	529
IAEA0871_03.009	SLOCON SOURCE PROGRAM	1101
IAEA0871_03.010	SLOCON TEST CASE INPUT DATA	20
IAEA0871_03.011	SLOCON TEST CASE PRINTED OUTPUT	182
IAEA0871_03.012	DISFAC SOURCE PROGRAM	279
IAEA0871_03.013	DISFAC TEST CASE INPUT DATA	1
IAEA0871_03.014	DISFAC TEST CASE PRINTED OUTPUT	49
IAEA0871_03.015	ODOG SOURCE PROGRAM	392
IAEA0871_03.016	ODOG TEST CASE INPUT DATA	7
IAEA0871_03.017	ODOG TEST CASE PRINTED OUTPUT	181
IAEA0871_03.018	ODMUG SOURCE PROGRAM	968
IAEA0871_03.019	ODMUG TEST CASE INPUT DATA	15
IAEA0871_03.020	ODMUG TEST CASE PRINTED OUTPUT	573
IAEA0871_03.021	FUELBURN SOURCE PROGRAM	384
IAEA0871_03.022	FUELBURN TEST CASE INPUT DATA	4
IAEA0871_03.023	FUELBURN TEST CASE PRINTED OUTPUT	290

File name	File description	Records
IAEA0871_04.001	Information file	210
IAEA0871_04.002	Batch file to run and compile NEMC	36
IAEA0871_04.003	Response file	12
IAEA0871_04.004	Cross reference file	319
IAEA0871_04.005	Binary library	0
IAEA0871_04.006	STAT48 sample input	23
IAEA0871_04.007	STAT49 sample input	23
IAEA0871_04.008	STATTEST sample input	450
IAEA0871_04.009	ALTDTR source file	62
IAEA0871_04.010	ANPAST source file	95
IAEA0871_04.011	BATEST source file	93
IAEA0871_04.012	BETA source file	85
IAEA0871_04.013	BETADT source file	68
IAEA0871_04.014	BINDTR source file	66
IAEA0871_04.015	CAUDTR source file	63
IAEA0871_04.016	CHFRAK source file	17
IAEA0871_04.017	CHIDTR source file	259
IAEA0871_04.018	CHIQUA source file	77
IAEA0871_04.019	CHITES source file	161
IAEA0871_04.020	COCTES source file	71
IAEA0871_04.021	CORRE source file	193
IAEA0871_04.022	DATA source file	5
IAEA0871_04.023	DGLDTR source file	64
IAEA0871_04.024	DLGAM source file	92
IAEA0871_04.025	EXPDTR source file	63
IAEA0871_04.026	FALTER source file	13
IAEA0871_04.027	FBETA1 source file	66
IAEA0871_04.028	FBETA2 source file	66
IAEA0871_04.029	FBINOM source file	69
IAEA0871_04.030	FCAUCH source file	66
IAEA0871_04.031	FDIGL1 source file	13
IAEA0871_04.032	FEXPO source file	68
IAEA0871_04.033	FFISCH source file	85
IAEA0871_04.034	FFRAK source file	20
IAEA0871_04.035	FGAMMA source file	70
IAEA0871_04.036	FGAUSS source file	68
IAEA0871_04.037	FHYPGE source file	70
IAEA0871_04.038	FISCHER source file	85
IAEA0871_04.039	FISDTR source file	64
IAEA0871_04.040	FKAUSA source file	18
IAEA0871_04.041	FPOISS source file	72
IAEA0871_04.042	FRAKTI source file	78
IAEA0871_04.043	FSTGL1 source file	12
IAEA0871_04.044	FSTUD source file	63
IAEA0871_04.045	FWEIBU source file	67
IAEA0871_04.046	GAMAIN source file	121
IAEA0871_04.047	GAMDTR source file	63
IAEA0871_04.048	GAMFAK source file	81
IAEA0871_04.049	GAUSS source file	28
IAEA0871_04.050	GFRAK source file	13
IAEA0871_04.051	HARTEST source file	64
IAEA0871_04.052	HYPDTR source file	67
IAEA0871_04.053	KAUDTR source file	64
IAEA0871_04.054	KLABEL source file	88
IAEA0871_04.055	KOLMO source file	140
IAEA0871_04.056	KONST source file	88
IAEA0871_04.057	LOC source file	75
IAEA0871_04.058	LTEST source file	106
IAEA0871_04.059	MINMAX source file	68
IAEA0871_04.060	MINV source file	172
IAEA0871_04.061	MPRD source file	85
IAEA0871_04.062	MSTR source file	87
IAEA0871_04.063	MTRA source file	76
IAEA0871_04.064	MULIRE source file	101
IAEA0871_04.065	MULTR source file	158
IAEA0871_04.066	NORDTR source file	62
IAEA0871_04.067	ORDER source file	86
IAEA0871_04.068	POIDTR source file	63
IAEA0871_04.069	POISSON source file	75
IAEA0871_04.070	RANK source file	111
IAEA0871_04.071	REGOUT source file	95
IAEA0871_04.072	REGTEST source file	34
IAEA0871_04.073	SGLDTR source file	62
IAEA0871_04.074	SMIRN source file	81
IAEA0871_04.075	SRANK source file	120
IAEA0871_04.076	STOUT source file	126
IAEA0871_04.077	STPRG source file	280
IAEA0871_04.078	STUDENT source file	61
IAEA0871_04.079	STUDTR source file	63
IAEA0871_04.080	TANPAS source file	49
IAEA0871_04.081	TFRAK source file	17
IAEA0871_04.082	TIE source file	99
IAEA0871_04.083	TVARVGL source file	29
IAEA0871_04.084	UEBER source file	82
IAEA0871_04.085	VALTER source file	11
IAEA0871_04.086	VARGL source file	109
IAEA0871_04.087	VBETA1 source file	138
IAEA0871_04.088	VBETA2 source file	65
IAEA0871_04.089	VBINOM source file	80
IAEA0871_04.090	VCAUCH source file	66
IAEA0871_04.091	VDIGL1 source file	16
IAEA0871_04.092	VERT source file	20
IAEA0871_04.093	VEXPO source file	67
IAEA0871_04.094	VFISCH source file	69
IAEA0871_04.095	VGAMMA source file	68
IAEA0871_04.096	VGAUSS source file	98
IAEA0871_04.097	VHYPGE source file	74
IAEA0871_04.098	VKAUSA source file	10
IAEA0871_04.099	VPOISS source file	69
IAEA0871_04.100	VSTGL1 source file	13
IAEA0871_04.101	VSTUD source file	68
IAEA0871_04.102	VWEIBU source file	65
IAEA0871_04.103	WEIDTR source file	66
IAEA0871_04.104	TANPAS sample output	513
IAEA0871_04.105	TFRAK sample output	43
IAEA0871_04.106	CHFRAK sample output	43
IAEA0871_04.107	CHIQUA sample output	129
IAEA0871_04.108	FFRAK sample output	56
IAEA0871_04.109	FISCHER sample output	1893
IAEA0871_04.110	GAUSS sample output	135
IAEA0871_04.111	GFRAK sample output	13
IAEA0871_04.112	POISSON sample output	125
IAEA0871_04.113	REGTEST sample output	149
IAEA0871_04.114	STUDENT sample output	125
IAEA0871_04.115	DISFAC sample input	1
IAEA0871_04.116	FARCON sample input	7
IAEA0871_04.117	FARLIB sample input	498
IAEA0871_04.118	FUBOR sample input	4
IAEA0871_04.119	ODMUG sample input	16
IAEA0871_04.120	SLOWCON sample input	20
IAEA0871_04.121	ZUZU sample input	7
IAEA0871_04.122	DISFAC source file	279
IAEA0871_04.123	FARCON source file	344
IAEA0871_04.124	FUBOR source file	374
IAEA0871_04.125	ODMUG source file	967
IAEA0871_04.126	SLOWCON source file	1108
IAEA0871_04.127	VPILIB source file	53
IAEA0871_04.128	ZUZU source file	392
IAEA0871_04.129	DISFAC sample output	52
IAEA0871_04.130	FARCON sample output	546
IAEA0871_04.131	FUBOR sample output	312
IAEA0871_04.132	ODMUG sample output	628
IAEA0871_04.133	SLOWCON sample output	182
IAEA0871_04.134	VPILIB sample output	508
IAEA0871_04.135	ZUZU sample output	183
IAEA0871_04.136	Batch file to compile and link	17
IAEA0871_04.137	FARLIB Binary library	0
IAEA0871_04.138	DOS file-names	137