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PSR-0315 AMPX-77.

AMPX-77, Modular System for Coupled Neutron-Gamma MultiGroup Cross-Sections from ENDF/B-5

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1. NAME OR DESIGNATION OF PROGRAM:  AMPX-77 (Modular Code System for
Generating Coupled Multigroup Neutron-Gamma Libraries from ENDF/B).
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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
AMPX-77 PSR-0315/01 Arrived 03-MAY-2002

Machines used:

Package ID Orig. computer Test computer
PSR-0315/01 Many Computers
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3. DESCRIPTION OF PROGRAM OR FUNCTION

The AMPX system is a system of  computer programs (modules) capable of producing coupled multigroup  neutron-gamma-ray cross section sets. The system is one of the standards for producing multigroup neutron, gamma-ray production, gamma-ray interaction, and coupled neutron-gamma cross-section sets  from ENDF data. AMPX-produced cross sections can be used directly with a variety of diffusion theory, discrete ordinates, and Monte Carlo radiation transport computer codes. A one-dimensional Sn calculation capability is provided for general use and for cross section collapsing. Treatments are included for resonance self-shielding effects.
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4. METHOD OF SOLUTION

The system includes a full range of features needed to: (1) produce multigroup neutron, gamma-ray production, and/or gamma-ray interaction cross-section data, (2) resonance self-shield, (3) spectrally collapse, (4) convert cross-section libraries from one format to another format, (5) execute a one- dimensional (1-D) discrete-ordinates calculation, and (6) perform miscellaneous cross section-operations.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The principal restriction is the availability of adequate core storage. All large  modules are variably dimensioned. Certain modules will automatically use external storage (disk,tape), if in-core storage is inadequate.  While these procedures are of little consequence on today's large computers with "virtual memory" capabilities, they can be important  when small-core PC's or workstations are used.
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6. TYPICAL RUNNING TIME

Running times are extremely problem dependent and depend heavily on the modules selected.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

The primary AMPX-77 modules support Version 5 and earlier, although it is possible to process many Version 6 evaluations. There are 47 modules in the AMPX-77 system. A partial list follows.

AUXILIARY ROUTINES:

AIM: Converts master cross-section libraries from BCD to binary format (or vice-versa).

ALPO: Produces ANISN libraries from AMPX master libraries.

ALE: Produces listings of data from AMPX master and working interfaces.

AJAX: Merges, collects, reorders, joins, and/or copies selected data sets from AMPX master interfaces.

BONAMI: Resonance Self-shielding by the Bondarenko Method.

COMAND: Collapses ANISN cross-section libraries.

CONTAC: Produces ANISN or CCCC ISOTXS libraries from AMPX working libraries.

ICE-2: Mixes cross sections on an AMPX working library and produces a macroscopic AMPX working library, ANISN libraries, or group-independent ANISN cross-section libraries.

LAPHNGAS: Generates multigroup secondary gamma-ray production cross sections and/or multiplicities from ENDF/B point data.

LAVA: Produces an AMPX working library form an ANISN cross-section library.

MALOCS: Collapses fine-group AMPX master libraries into broad-group AMPX master libraries.

NITAWL-II: Converts from the AMPX master library format to an AMPX working library. Optionally, it will perform a Nordheim integral treatment calculation for nuclides with resonance parameters.

RADE: Used to perform checks on AMPX master, AMPX working, and ANISN libraries.

ROLAIDS: Performs an integral transport calculation for the energy-pointwise, slowing-down flux distribution in each zone of a 1-D, multiregion geometry to produce multigroup resonance-shielded constants.

SMILER: Converts NJOY GENDF files to AMPX master libraries.

SMUG: Generates a photon-interaction master library from ENDF/B data.

TABU: Produces an AMPX master cross-section file which contains Bondarenko factor data for the unresolved energy region.

VASELINE: Produces plots of cross sections from ENDF/B libraries or from AMPX master or working libraries.

WAX: Collects data from one or more AMPX working libraries to create a new working library.

UNITAB: Combines data for a nuclide from more than one AMPX master library to create a new AMPX master library.

WORM: Reads an AMPX working library and reformats it to write an AMPX master library.

XLACS: Uses ENDF/B data to produce multigroup neutron cross sections on an AMPX master library.

XSDRNPM: Performs a 1-D discrete-ordinates or diffusion theory calculation using cross sections on an AMPX working library.
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9. STATUS
Package ID Status date Status
PSR-0315/01 03-MAY-2002 Masterfiled Arrived
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10. REFERENCES:
PSR-0315/01, included references:
- N.M. Greene, W.E. Ford III, L.M. Petrie and J.W. Arwood:
  AMPX-77 - A Modular Code System for Generating Coupled Multigroup
  Neutron-Gamma Cross-Section Libraries from ENDF/B-IV and/or
  ENDF/B-V
  ORNL/CSD/TM-283 (October 1992).
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11. MACHINE REQUIREMENTS

AMPX-77 is operable on the IBM 3090 and CRAY  computers. In the latter case, the modules have been used in both the CRAY CTSS and UNICOS environments. Many modules have been used on UNIX-based workstations such as the IBM RISC 6000, the DEC 5000 and the HP.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
PSR-0315/01 FORTRAN+ASSEMBLER
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED

AMPX-77 uses Fortran-77 and Assembler on the IBM system and Fortran-77 and some "C" on UNICOS systems. The IBM version was tested using the VS compiler (Level 2.2.0) and Assembler Level H running under OS/VS2. After processing with the conversion program included, the system was tested on a Cray under UNICOS using the CFT77 compiler. DISSPLA  software is required for VASELINE.
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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:   Oak Ridge National Laboratory, Oak Ridge, Tennessee, USA
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16. MATERIAL AVAILABLE
PSR-0315/01
README.NOW Information File                
README.GEN Gen. Instructions for IBM & Cray
README.CRA Instructions for Cray Users     
CRAYFORT.EXE Compress. File FTN Source Cray
IBMJCL.EXE Compress. File JCL & Input IBM  
CRAYJCL.EXE Compress. File JCL & Input Cray
DATA.EXE Compress. File ASCII Data IBM&Cray
SOURCE.EXE Compress. File Fortran Source   
OUTPUT.EXE Compress. File Output from Cray
DOCUMENTATION
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17. CATEGORIES
  • A. Cross Section and Resonance Integral Calculations
  • B. Spectrum Calculations, Generation of Group Constants and Cell Problems
  • C. Static Design Studies
  • J. Gamma Heating and Shield Design
  • K. Reactor Systems Analysis

Keywords: ENDF/B, cross sections, data processing, discrete ordinate method, gamma radiation, multigroup, neutrons, one-dimensional, resonance, self-shielding.