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IAEA0871 VPI-NECM.

VPI-NECM, Nuclear Engineering Program Collection for College Training

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1. NAME OR DESIGNATION OF PROGRAM:  VPI-NECM. Nuclear Engineering Computer Modules for in-core fuel management analysis.
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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
VPI-NECM IAEA0871/02 Tested 05-JUN-1985
VPI-NECM IAEA0871/03 Tested 12-JUN-1985
VPI-NECM IAEA0871/04 Tested 07-AUG-1991

Machines used:

Package ID Orig. computer Test computer
IAEA0871/02 CDC CYBER 73 CDC CYBER 740
IAEA0871/03 CDC CYBER 173 DEC VAX 11/780
IAEA0871/04 IBM PC PC-80386
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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.
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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.
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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.
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6. TYPICAL RUNNING TIME

The execution time of one module varies from  0.051 seconds to 1.479 seconds.
IAEA0871/02
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

IAEA0871/03
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
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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.
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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.
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9. STATUS
Package ID Status date Status
IAEA0871/02 05-JUN-1985 Tested at NEADB
IAEA0871/03 12-JUN-1985 Tested at NEADB
IAEA0871/04 07-AUG-1991 Tested at NEADB
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10. REFERENCES

- S.H. Levine,
  MODULE-5 "In-Core Management", Editer N.D. Eckhot Kansas State
  University, 1980.
IAEA0871/02, included references:
- 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
IAEA0871/03, included references:
- 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"
IAEA0871/04, included references:
- 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"
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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.
IAEA0871/02
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

IAEA0871/03
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

IAEA0871/04
The test cases were executed on a PC/80386 compatible desktop computer with a 80387 math coprocessor.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA0871/02 FORTRAN
IAEA0871/03 FORTRAN-IV
IAEA0871/04 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  SCOPE 3.4. It can work also under NOS.
IAEA0871/02
NOS 1.4-531 (CDC CYBER 740).

IAEA0871/03
VMS-V3.4 (VAX-11/780).

IAEA0871/04
MSDOS-4.01 with Microsoft FORTRAN 5.0 compiler.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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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.
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16. MATERIAL AVAILABLE
IAEA0871/02
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
IAEA0871/03
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
IAEA0871/04
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
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17. CATEGORIES
  • C. Static Design Studies
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics
  • F. Space - Time Kinetics, Coupled Neutronics - Hydrodynamics - Thermodynamics
  • G. Radiological Safety, Hazard and Accident Analysis
  • K. Reactor Systems Analysis

Keywords: burnup, cost, criticality, fuel management, neutron diffusion equation, nuclear engineering, reactor dynamics, reactor kinetics, reactor lattices, reactor safety, reactor stability, slowing-down.