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NEA-0546 APPLE-2.

APPLE, Plot of 1-D MultiGroup Neutron Flux and Gamma Flux and Reaction Rates from ANISN

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1. NAME OR DESIGNATION OF PROGRAM:  APPLE-2.
An improved version of the APPLE code for plotting neutron and gamma ray spectra and reaction rates.
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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
APPLE-2 NEA-0546/03 Tested 19-SEP-1983

Machines used:

Package ID Orig. computer Test computer
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.
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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.
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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
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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.
NEA-0546/03
NEA-DB executed the test case included in this package  on IBM 3081K in 5 CPU seconds.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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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.
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9. STATUS
Package ID Status date Status
NEA-0546/03 19-SEP-1983 Tested at NEADB
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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)
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.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0546/03 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  MVS-SP (IBM3081K)
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

Hiromitsu Kawasaki and Yasushi Seki
Division of Large Tokamak Development
Tokai Research Establishment
Japan Atomic Energy Research Institute
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16. MATERIAL AVAILABLE
NEA-0546/03
File name File description Records
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
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17. CATEGORIES
  • C. Static Design Studies
  • N. Subsidiary Calculations

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