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RSIC CODE PACKAGE PSR-332

1. NAME AND TITLE

 PRE-ANISN: A Preprocessing Code for ANISN and Other Radiation Transport Codes.
 
 

2. CONTRIBUTOR

 National Accelerator Centre, Republic of South Africa.
 
 

3. CODING LANGUAGE AND COMPUTER

 An interactive, personal computer-based preprocessing code, PRE-ANISN, was developed to automate the task of preparing source term and response conversion factor input for several radiation transport and transport related codes. The code prepares multigroup source spectra for SORREL, and multigroup volume distributed fixed source arrays for the 1-dimensional discrete ordinates transport  codes ANISN and XSDRNPM.  It prepares multigroup fluence rate to response conversion factors for AXMIX, (a cross-section preprocessing code for ANISN and DOT 3.5), ANISN and DOT 3.5. PRE-ANISN also prepares source terms and response conversion factors for adjoint transport calculations.
 

4. NATURE OF PROBLEM SOLVED

See PRE-ANISN documentation for details.
 

5. METHOD OF SOLUTION

 Preparing a multigroup spectrum:

 If a built-in or user-supplied source spectrum is selected, multigroup source-spectra are determined by numerically integrating the chosen spectrum function over the energy partition. (Integration scheme: Simpson's method.) If a tabular source spectrum is supplied, a linear function is formed by linear interpolation between the supplied (Energyital i,Spectrumital i) data points. Integration then proceeds as above.

 Preparing a 1-dimensional multigroup volume-distributed fixed source:

 It is assumed that the energy & spatial dependence of the source term is separable, i.e. Bold ITAL Q (Bold ITAL E,ital x) alpha Bold ITAL N(Bold ITAL E) Bold ITAL P(ital x). The 1-D volume-distributed fixed source isBold ITAL Q sub ital {gi} = Bold ITAL N sub ital g Bold ITAL P (x bar sub ital i), where Bold ITAL N sub ital g is the multigroup energy spectrum calculated in the previous step, and x bar sub ital i is the midpoint of the ital i'th spatial interval. The spatial power distribution function ITAL P(ital x) is formed by linearly interpolating between relative power values specified at certain locations inside the source region.

 Preparing a multigroup response function:

 The response function is evaluated at the midpoint of every energy group. Linear interpolation is used between the data pairs of tabular response functions.
 
 

6. RESTRICTIONS OR LIMITATIONS

 Maximum number of energy groups: 130

 Maximum number of spatial intervals: 1000

 Maximum length of spectrum table or response function table: 1500 data pairs. The assumption is made that the energy and spatial dependence of the source term is separable.
 
 

7. TYPICAL RUNNING TIME

 One to five minutes on a 33 MGz 80406DX PC. The numerical integration required to evaluate the spectrum integrals takes about 75% of this time.
 
 

8. COMPUTER HARDWARE REQUIREMENTS

 An 80ital x86 PC with ital x >= 3, a hard disk and at least 4 MBytes of RAM. A 1 MByte ramdisk speeds up I/O considerably. A math-coprocessor is necessary for use with the supplied executable. There are no special graphics as printing capabilities, therefore a CGA or better with a dot matrix lineprinter is sufficient.
 
 

9. COMPUTER SOFTWARE REQUIREMENTS

 The Lahey F77L-EM/32 version 5.01 was used to compile the PRE-ANISN source code. PharLap DOS Extender was used to link the PRE-ANISN object file to extended memory managers. The executables requires an external error file "F77L3.EER" to be present when running PRE-ANISN under supplied with the distribution diskette.
 
 

10. REFERENCE

 Van Rooyen, T.J., "PRE-ANISN, A Preprocessing Code for ANISN and Other Radiation Transport Codes," NAC Report NAC/91-06 (December 1991).
 
 

11. CONTENTS OF CODE PACKAGE

 Included are the referenced document and a 5.25-in. DS/HD (1.2MB) diskette which includes source program, executable, sample input and output files in compressed mode.
 
 

12. DATE OF ABSTRACT

 March 1993.
 
 

KEYWORDS: MULTIGROUP; ANISN; PREPROCESSING; CODE; SPECTRUM; SOURCE TERM; RESPONSE; CONVERSION FACTOR; VOLUME DISTRIBUTED FIXED SOURCE; RADIATION TRANSPORT CALCULATIONS; DOSE RATE