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[Program Service | Recent programs]

CCC-0639 RACC-PULSE. (Abstract last modified 27-NOV-2001)


RACC-PULSE, Neutron Activation in Fusion Reactor System

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Abstract Table of Contents:

NAME | COMPUTER | PROBLEM | SOLUTION | RESTRICTIONS | CPU | FEATURES | AUXILIARIES | STATUS | REFERENCES | REQUIREMENTS | LANGUAGE | OPERATING SYSTEM | OTHER RESTRICTIONS | AUTHOR | MATERIAL | CATEGORIES |

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1. NAME OR DESIGNATION OF PROGRAM - RACC-PULSE. 


2. COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE -

To request or retrieve programs click on the one of the active versions below. A password and special authorization is required.

Explanation of the status codes.

Program-name         Package-ID  Status
RACC-PULSE           CCC-0639/01 Arrived

Machines used:
Package-ID     Orig.Computer                       Test Computer
CCC-0639/01    UNIX gen. W.S.                      

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.


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.


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.


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.


7. UNUSUAL FEATURES OF THE PROGRAM - 


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 


9. STATUS
CCC-0639/01: 27-NOV-2001 Masterfiled Arrived


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:
- 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)


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.


12. PROGRAMMING LANGUAGE(S) USED -
CCC-0639/01: FORTRAN-77 


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.


14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS - 


15. NAME AND ESTABLISHMENT OF AUTHORS - 
Contributed by: 
                Radiation Shielding Information Center 
                Oak Ridge National Laboratory 
                Oak Ridge, Tennessee, U. S. A. 
Developed by: 
                University of Wisconsin, Madison, Wisconsin, U.S.A. 


16. MATERIAL AVAILABLE -
CCC-0639/01:
C639READ.ME Information file               
C639TAR0.LIS List of files                 
C639TAR0.Z Compressed UNIX tar file        
convertflux.f FTN source for auxiliary code
raccdlib Decay constant data               
raccxlib Transmutation cross section data  
fluxin Scalar fluxin for sample problem    
iracc Sample input problem                 
oracc.cray Sample output from Cray-2       
oracc.workstation Sample out. from DEC5000 
densolver1.f FORTRAN source (for Cray)     
densolver2.f FORTRAN source (for Cray)     
ematrix.f FORTRAN source (for Cray)        
makefile Makefile for Cray (for Cray)      
param_racc FORTRAN source (for Cray)       
owerm.f FORTRAN source (for Cray)          
Racc.new.f FORTRAN source (for Cray)       
Schur.f FORTRAN source (for Cray)          
densolver1.f FORTRAN source (for W.S.)     
densolver2.f FORTRAN source (for W.S.)     
ematrix.f FORTRAN source (for W.S.)        
makefile Makefile for Cray (for W.S.)      
param_racc FORTRAN source (for W.S.)       
owerm.f FORTRAN source (for W.S.)          
Racc.new.f FORTRAN source (for W.S.)       
Schur.f FORTRAN source (for W.S.)          
prog. note               README.RSI (April 1995)                    NOTPT
report                   UWFDM-980 (May 1995)                       REPPT
report                   ANL/FPP-TM-122 (May 1979)                  REPPT


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

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