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CCC-0639 RACC-PULSE.

RACC-PULSE, Neutron Activation in Fusion Reactor System

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1. NAME OR DESIGNATION OF PROGRAM:  RACC-PULSE.
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2. COMPUTERS
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Program name Package id Status Status date
RACC-PULSE CCC-0639/01 Arrived 27-NOV-2001

Machines used:

Package ID Orig. computer Test computer
CCC-0639/01 UNIX W.S.
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3. DESCRIPTION OF PROGRAM OR FUNCTION

CCC-0388/RACC was specifically  developed to compute the radioactivity and radioactivity-related parameters (e.g. afterheat, biological hazard potential, etc.) due to neutron activation within Inertial Fusion Energy and Magnetic Fusion energy reactor systems. It can also be utilized to compute the radioactivity in fission, accelerator or any other neutron generating and neutron source system. This new designated RACC-PULSE is based on CCC-0388 and has the capability to model irradiation histories of varying flux levels having varying pulse widths (on times) and dwell periods (off times) and varying maintenance periods. This provides the user with the flexibility of modeling most any complexity of irradiation history beginning with simple steady state operating systems to complex multi-flux level pulse/intermittent operating systems.
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4. METHOD OF SOLUTION

The solution method implemented within the RACC-PULSE code is a matrix based method which relies on the evaluation of the Matrix Exponential for the pulse period (on period), dwell period (off time) and post shutdown periods. For the  pulsed and dwell periods, the Matrix Exponential was evaluated using the squaring and scaling technique outlined in a review article by Molar and Van Loan entitled "Nineteen Dubious Ways to Compute the Exponential of a Matrix". A balanced binary tree method utilized for parameter storage in information systems was employed to evaluate the linear chains constructed for the post shutdown period. The RACC-Pulse code retains the capability of modeling the standard slab, cylinder, sphere and torus geometries in multidimensions as well as the point or zero-dimension geometry for Monte Carlo code interfacing. It provides easy interfacing with many of the standard  multigroup, multidimensional neutron/photon transport code systems currently employed by the fusion community and implemented on the UNICOS Cray 2 System at NERSC. An auxiliary code is provided to interface between the Los Alamos National Laboratory CCC-0547/ DANTSYS transport codes for users running on UNIX workstations. RACC-Pulse retains the FIDO formatted style of data input.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The user of the code is encouraged to update the transmutation library as it contains only a subset of reactions from the USACT 93 library. The library lacks the gamma photon emission intensity data required for the generation of the gamma source output.
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6. TYPICAL RUNNING TIME

The typical run time is one half to one hour  for simple 1-dimensional 15 zone, 600 fine mesh problems. Large detailed 2-dimensional problems are projected to run for one to several hours. The actual run time depends on the operating history  of the reactor being modeled. The more complex the operating history the longer the run time.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

AUXILIARY ROUTINE
    CONVERTFLUX: Routine to convert ONEDANT and TWODANT flux data
DATA LIBRARIES
    raccdlib:    Decay constant data
    raccxlib:    Transmutation cross section data
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9. STATUS
Package ID Status date Status
CCC-0639/01 27-NOV-2001 Masterfiled Arrived
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10. REFERENCES

- SIAM Review, 20, 801 (October 1978)
- Q. Wang and D.L. Henderson:
  Summary Report for ITER Design Task DIO: Updating the Activation
  Code RACC for ITER Design Analysis
  UWFDM-977 (January 1995)
CCC-0639/01, included references:
- M.E. Newman:
  README.RSI (April 1995)
- Q. Wang and D.L. Henderson:
  RACC-Pulse: A Version of the RACC Radioactivity Code for Pulsed
  Intermittent Activity Analysis
  UWFDM-980 (May 1995)
- J. Jung:
  Theory and Use of the Radioactivity Code RACC
  ANL/FPP-TM-122 (May 1979)
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11. MACHINE REQUIREMENTS

RACC-PULSE runs on the CRAY 2 UNICOS computer and DEC 5000 and HP 7000 series UNIX workstations. The code is memory intensive, hence workstation systems containing 32 MB of RAM  or more are required for large problems.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
CCC-0639/01 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

A FORTRAN 77 compiler is required. RACC-PULSE was tested at RSIC using the included sample input files on an IBM RS/6000 Model 590 running AIX  3.2.5 using XL FORTRAN v3.2.2.3. It was also tested at RSIC on a DEC 5000 running Ultrix 4.5 using DEC FORTRAN for RISC/Ultrix v.3.2.
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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:   University of Wisconsin, Madison, Wisconsin, U.S.A.
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16. MATERIAL AVAILABLE
CCC-0639/01
miscellaneous    mag tapeC639READ.ME Information file               MISTP
miscellaneous    mag tapeC639TAR0.LIS List of files                 MISTP
miscellaneous    mag tapeC639TAR0.Z Compressed UNIX tar file        MISTP
source program   mag tapeconvertflux.f FTN source for auxiliary codeSRCTP
test-case data   mag taperaccdlib Decay constant data               DATTP
test-case data   mag taperaccxlib Transmutation cross section data  DATTP
test-case data   mag tapefluxin Scalar fluxin for sample problem    DATTP
test-case data   mag tapeiracc Sample input problem                 DATTP
test-case output mag tapeoracc.cray Sample output from Cray-2       OUTTP
test-case output mag tapeoracc.workstation Sample out. from DEC5000 OUTTP
source program   mag tapedensolver1.f FORTRAN source (for Cray)     SRCTP
source program   mag tapedensolver2.f FORTRAN source (for Cray)     SRCTP
source program   mag tapeematrix.f FORTRAN source (for Cray)        SRCTP
test-case data   mag tapemakefile Makefile for Cray (for Cray)      DATTP
source program   mag tapeparam_racc FORTRAN source (for Cray)       SRCTP
source program   mag tapeowerm.f FORTRAN source (for Cray)          SRCTP
source program   mag tapeRacc.new.f FORTRAN source (for Cray)       SRCTP
source program   mag tapeSchur.f FORTRAN source (for Cray)          SRCTP
source program   mag tapedensolver1.f FORTRAN source (for W.S.)     SRCTP
source program   mag tapedensolver2.f FORTRAN source (for W.S.)     SRCTP
source program   mag tapeematrix.f FORTRAN source (for W.S.)        SRCTP
test-case data   mag tapemakefile Makefile for Cray (for W.S.)      DATTP
source program   mag tapeparam_racc FORTRAN source (for W.S.)       SRCTP
source program   mag tapeowerm.f FORTRAN source (for W.S.)          SRCTP
source program   mag tapeRacc.new.f FORTRAN source (for W.S.)       SRCTP
source program   mag tapeSchur.f FORTRAN source (for W.S.)          SRCTP
prog. note               README.RSI (April 1995)                    NOTPT
report                   UWFDM-980 (May 1995)                       REPPT
report                   ANL/FPP-TM-122 (May 1979)                  REPPT
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics
  • X. Magnetic Fusion Research

Keywords: activation, biological hazard potential, fusion reactors, health hazards, neutron reactions, radioactive decay, radioisotopes.