NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROBLEM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES

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Program name | Package id | Status | Status date |
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APPLE-2 | NEA-0546/03 | Tested | 19-SEP-1983 |

Machines used:

Package ID | Orig. computer | Test computer |
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NEA-0546/03 | IBM 3081 | IBM 3081 |

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3. DESCRIPTION OF PROBLEM OR FUNCTION

The APPLE-2 code has the following functions:

(1) It plots multi-group energy spectra of neutron and/or gamma ray fluxes calculated by ANISN, DOT-3.5, and MORSE.

(2) It gives an overview plot of multi-group neutron fluxes calculated by ANISN and DOT-3.5. The scalar neutron flux phi(r,E) is plotted with the spatial parameter r linear along the Y-axis, logE along the X-axis and log phi(r,E) in the Z direction.

(3) It calculates the spatial distribution and region volume integrated values of reaction rates using the scalar flux calculated with ANISN and DOT-3.5.

(4) Reaction rate distribution along the R or Z direction may be plotted.

(5) An overview plot of reaction rates or scalar fluxes summed over specified groups may be plotted. R(ri,zi) or phi(ri,zi) is plotted with spatial parameters r and z along the X- and Y-axes in an orthogonal coordinate system.

(6) Angular flux calculated by ANISN is rearranged and a shell source at any specified spatial mesh point may be punched out in FIDO format. The shell source obtained may be employed in solving deep penetration problems with ANISN, when the entire reactor system is divided into two or more parts and the neutron fluxes in two adjoining parts are connected by using the shell source.

The APPLE-2 code has the following functions:

(1) It plots multi-group energy spectra of neutron and/or gamma ray fluxes calculated by ANISN, DOT-3.5, and MORSE.

(2) It gives an overview plot of multi-group neutron fluxes calculated by ANISN and DOT-3.5. The scalar neutron flux phi(r,E) is plotted with the spatial parameter r linear along the Y-axis, logE along the X-axis and log phi(r,E) in the Z direction.

(3) It calculates the spatial distribution and region volume integrated values of reaction rates using the scalar flux calculated with ANISN and DOT-3.5.

(4) Reaction rate distribution along the R or Z direction may be plotted.

(5) An overview plot of reaction rates or scalar fluxes summed over specified groups may be plotted. R(ri,zi) or phi(ri,zi) is plotted with spatial parameters r and z along the X- and Y-axes in an orthogonal coordinate system.

(6) Angular flux calculated by ANISN is rearranged and a shell source at any specified spatial mesh point may be punched out in FIDO format. The shell source obtained may be employed in solving deep penetration problems with ANISN, when the entire reactor system is divided into two or more parts and the neutron fluxes in two adjoining parts are connected by using the shell source.

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4. METHOD OF SOLUTION

(a) The input data specification is made as simple as possible by making use of the input data required in the radiation transport code. For example, geometry related data in ANISN and DOT are transmitted to APPLE-2 along with scalar flux data so as to reduce duplicity and errors in reproducing these data.

(b) Most the input data follow the free form FIDO format developed at Oak Ridge National Laboratory and used in the ANISN code.

Furthermore, the mixture specifying method used in ANISN is also employed by APPLE-2.

(c) Libraries for some standard response functions required in fusion reactor design have been prepared and are made available to users of the 42-group neutron, 21-group gamma ray coupled cross section set GICX40. For fluxes calculated with arbitrary cross sections, response functions must be supplied by card input.

(d) When drawing energy spectra of fluxes calculated with the GICX40 set, there is no need to input energy group structure data as they are built into the APPLE-2 code.

(e) Reaction rates calculated with more than one flux may be drawn on a graph for comparison.

(f) The graphical outputs are devised so that they may readily be used in reports.

(a) The input data specification is made as simple as possible by making use of the input data required in the radiation transport code. For example, geometry related data in ANISN and DOT are transmitted to APPLE-2 along with scalar flux data so as to reduce duplicity and errors in reproducing these data.

(b) Most the input data follow the free form FIDO format developed at Oak Ridge National Laboratory and used in the ANISN code.

Furthermore, the mixture specifying method used in ANISN is also employed by APPLE-2.

(c) Libraries for some standard response functions required in fusion reactor design have been prepared and are made available to users of the 42-group neutron, 21-group gamma ray coupled cross section set GICX40. For fluxes calculated with arbitrary cross sections, response functions must be supplied by card input.

(d) When drawing energy spectra of fluxes calculated with the GICX40 set, there is no need to input energy group structure data as they are built into the APPLE-2 code.

(e) Reaction rates calculated with more than one flux may be drawn on a graph for comparison.

(f) The graphical outputs are devised so that they may readily be used in reports.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Variable

dimensioning is employed in APPLE. There is no practical limitation to the number of reaction rates to be calculated and plotted on a graph, but the same type of plot symbol will appear for every 17th reaction rate curve.

If a problem requiring a core size larger than 50 kwords is to be solved, two cards in the FTMAIN routine of APPLE specifying blank common should be changed:

COMMON D(XXXXX)

LIMM=XXXXX

Variable

dimensioning is employed in APPLE. There is no practical limitation to the number of reaction rates to be calculated and plotted on a graph, but the same type of plot symbol will appear for every 17th reaction rate curve.

If a problem requiring a core size larger than 50 kwords is to be solved, two cards in the FTMAIN routine of APPLE specifying blank common should be changed:

COMMON D(XXXXX)

LIMM=XXXXX

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6. TYPICAL RUNNING TIME

The sample problem using ANISN calculated fluxes, which is included in the code package, required about 1 minute on FACOM M-200.

The sample problem using ANISN calculated fluxes, which is included in the code package, required about 1 minute on FACOM M-200.

NEA-0546/03

NEA-DB executed the test case included in this package on IBM 3081K in 5 CPU seconds.[ top ]

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8. RELATED AND AUXILIARY PROGRAMS

(1) CALCOMP plotting routines

(2) modified FINPR subroutine for ANISN

(3) modified OUTER, TPSAVE, TPXF subroutines for DOT-3.5

(4) modified NRUN subroutine for MORSE.

AUXILIARY DATA LIBRARIES:

(1) GICXKRMA: 42-group neutron, 21-group gamma-ray kerma factor library

(2) XS63: Response library for fusion reactor neutronics calculation

(3) XS100: 100-group neutron responses

(4) GFLXDOSE: 54-group gamma-ray flux to dose conversion factors.

(1) CALCOMP plotting routines

(2) modified FINPR subroutine for ANISN

(3) modified OUTER, TPSAVE, TPXF subroutines for DOT-3.5

(4) modified NRUN subroutine for MORSE.

AUXILIARY DATA LIBRARIES:

(1) GICXKRMA: 42-group neutron, 21-group gamma-ray kerma factor library

(2) XS63: Response library for fusion reactor neutronics calculation

(3) XS100: 100-group neutron responses

(4) GFLXDOSE: 54-group gamma-ray flux to dose conversion factors.

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10. REFERENCES

- Yasushi Seki, Hideo Narita and Masahito Igarashi:

Computer Code APPLE for Plotting Spatial Distribution of Neutron

Spectra and Reaction Rates

JAERI-M 6365 (1976) (In Japanese)

- W.W. Engle, Jr.:

"A User's Manual for ANISN, A One-Dimensional Discrete Ordinates

Transport Code with Anisotropic Scattering"

ORNL K-1693 (1967)

- W.A. Rhoades and F.R. Mynatt:

"The DOT-3 Two-Dimensional Discrete Ordinates Transport Code"

ORNL/TM-4280 (1973)

- E.A. Straker et al.:

"The MORSE Code, A Multigroup Neutron and Gamma Ray Monte Carlo

Transport Code"

ORNL-4585 (1970)

- Yasushi Seki and Hiromasa Iida:

"Coupled 42-Group Neutron and 21-Group Gamma-Ray Cross Section

Sets for Fusion Reactor Calculations"

JAERI-M 8818 (1980)

- Yasushi Seki, Hideo Narita and Masahito Igarashi:

Computer Code APPLE for Plotting Spatial Distribution of Neutron

Spectra and Reaction Rates

JAERI-M 6365 (1976) (In Japanese)

- W.W. Engle, Jr.:

"A User's Manual for ANISN, A One-Dimensional Discrete Ordinates

Transport Code with Anisotropic Scattering"

ORNL K-1693 (1967)

- W.A. Rhoades and F.R. Mynatt:

"The DOT-3 Two-Dimensional Discrete Ordinates Transport Code"

ORNL/TM-4280 (1973)

- E.A. Straker et al.:

"The MORSE Code, A Multigroup Neutron and Gamma Ray Monte Carlo

Transport Code"

ORNL-4585 (1970)

- Yasushi Seki and Hiromasa Iida:

"Coupled 42-Group Neutron and 21-Group Gamma-Ray Cross Section

Sets for Fusion Reactor Calculations"

JAERI-M 8818 (1980)

NEA-0546/03, included references:

- H. Kawasaki and Y. Seki:APPLE-2: An Improved Version of APPLE Code for Plotting Neutron

and Gamma Ray Spectra and Reaction Rates.

JAERI-M 82-091 (July 1982)

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11. MACHINE REQUIREMENTS

APPLE-2 is designed and operable on FACOM M-200 series computers with CALCOMP PLOTTER 900. Maximum core requirements for the sample problem in the code package is less than 128 kwords. Auxiliary storage requirements, in addition to standard input and output devices, are 5 storage devices and one or more additional tapes or disks for scalar flux input.

NEA 0546/03: To execute the test case on IBM 3081K, 404K bytes of main storage are required.

APPLE-2 is designed and operable on FACOM M-200 series computers with CALCOMP PLOTTER 900. Maximum core requirements for the sample problem in the code package is less than 128 kwords. Auxiliary storage requirements, in addition to standard input and output devices, are 5 storage devices and one or more additional tapes or disks for scalar flux input.

NEA 0546/03: To execute the test case on IBM 3081K, 404K bytes of main storage are required.

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NEA-0546/03

File name | File description | Records |
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NEA0546_03.003 | APPLE-2 INFORMATION FILE | 135 |

NEA0546_03.004 | APPLE-2 SOURCE CARD-IMAGES (FORTRAN-4) | 5169 |

NEA0546_03.005 | GICXKRMA LIBRARY (FORMATTED) | 1263 |

NEA0546_03.006 | XS63 LIBRARY (FORMATTED) | 97 |

NEA0546_03.007 | XS100 LIBRARY | 86 |

NEA0546_03.008 | GFLXDOSE LIBRARY (FORMATTED) | 13 |

NEA0546_03.009 | APPLE-2 INPUT FOR TEST CASE | 65 |

NEA0546_03.010 | APPLE-2 OUTPUT OF TEST CASE | 788 |

NEA0546_03.011 | COMV SOURCE | 31 |

NEA0546_03.012 | SCALAR FLUX OF ANISN OUTPUT (EBCDIC) | 1247 |

NEA0546_03.013 | DOT INPUT DATA | 68 |

NEA0546_03.014 | MORSE INPUT DATA | 21 |

NEA0546_03.015 | ANISN AUXILIARY ROUTINES | 261 |

NEA0546_03.016 | DOT-3.5 AUXILIARY ROUTINES | 437 |

NEA0546_03.017 | MORSE AUXILIARY ROUTINES | 486 |

NEA0546_03.018 | SETB99 SOURCE | 100 |

NEA0546_03.019 | APPLE-2 JCL FOR TEST CASE | 47 |

NEA0546_03.020 | ANISN BINARY FLUX (RECFM=VBS,BLKSIZE=13028) | 3 |

Keywords: angular distribution, computer graphics, gamma radiation, multigroup, neutron spectra, one-dimensional, plotting, reaction kinetics.