CCC-0639 RACC-PULSE.
RACC-PULSE, Neutron Activation in Fusion Reactor System
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM 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 AUTHORS, MATERIAL, CATEGORIES
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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.
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.
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.
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.
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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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)
- 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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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.
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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CCC-0639/01
miscellaneous mag tapeC639READ.ME Information file MISTPmiscellaneous 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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- 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.