PSR-0315 AMPX-77. (Abstract last modified 03-MAY-2002)
1.
NAME OR DESIGNATION OF PROGRAM - AMPX-77 (Modular Code System for 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.
Machines used:
Package-ID Orig.Computer Test Computer
PSR-0315/01 Many Computers
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.
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.
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.
6.
TYPICAL RUNNING TIME - Running times are extremely problem dependent and depend heavily on the modules selected.
7.
UNUSUAL FEATURES OF THE PROGRAM - 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.
9.
STATUS 10.
REFERENCES - 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.
12.
PROGRAMMING LANGUAGE(S) USED - 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.
14.
OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS - 15.
NAME AND ESTABLISHMENT OF AUTHORS - 16.
MATERIAL AVAILABLE - 17.
CATEGORIES - Keywords: CROSS SECTIONS, DATA PROCESSING, DISCRETE ORDINATE METHOD, ENDF/B, GAMMA RADIATION, MULTIGROUP, NEUTRONS, ONE-DIMENSIONAL, RESONANCE, SELF-SHIELDING
Generating Coupled Multigroup Neutron-Gamma Libraries from ENDF/B).
Program-name Package-ID Status
AMPX-77 PSR-0315/01 Arrived
PSR-0315/01:
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.
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 from 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 distri-
bution in each zone of a 1-D, multiregion
geometry to produce multigroup resonance-
shielded constants.
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.
PSR-0315/01: 03-MAY-2002 Masterfiled Arrived
PSR-0315/01:
- 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).
PSR-0315/01: FORTRAN+ASSEMBLER
Contributed by:
Radiation Shielding Information Center
Oak Ridge National Laboratory
Oak Ridge, Tennessee, U. S. A.
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
report ORNL/CSD/TM-283 (October 1992) REPPT
- 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
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