Sample problems for the novice user of the AMPX-II system. [For generating coupled multigroup neutron--gamma libraries, in FORTRAN IV for IBM 360/91]

Technical Report · Mon Jan 01 00:00:00 EST 1979

DOI:https://doi.org/10.2172/6519098· OSTI ID:6519098

Ford, III, W E; Roussin, R W; Petrie, L M; Diggs, B R; Comolander, H E

Contents of the IBM version of the APMX system distributed by the Radiation Shielding Information Center (APMX-II) are described. Sample problems which demonstrate the procedure for implementing AMPX-II modules to generate point cross sections; generate multigroup neutron, photon production, and photon interaction cross sections for various transport codes; collapse multigroup cross sections; check, edit, and punch multigroup cross sections; and execute a one-dimensional discrete ordinates transport calculation are detailed. 25 figures, 9 tables.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6519098
• Report Number(s): ORNL/CSD/TM-72; TRN: 79-004467
• Country of Publication: United States
• Language: English

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
COMPUTER CODES
A CODES
NEUTRON TRANSPORT
PHOTON TRANSPORT
SHIELDING
CROSS SECTIONS
DISCRETE ORDINATE METHOD
FORTRAN
IBM COMPUTERS
MULTIGROUP THEORY
COMPUTERS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT THEORY
PROGRAMMING LANGUAGES
RADIATION TRANSPORT
TRANSPORT THEORY
654002* - Radiation & Shielding Physics- Shielding Calculations & Experiments- (-1987)
654001 - Radiation & Shielding Physics- Radiation Physics
Shielding Calculations & Experiments
654003 - Radiation & Shielding Physics- Neutron Interactions with Matter