ARC-XSEC1; microscopic cross section manipulation. [IBM360; FORTRAN IV]

Technical Report ·

OSTI ID:6212608

Fowler, T B; Tobias, M L; Fox, J N; Lawler, B E; Koppel, J U; Triplett, J R; Lynn, L L; Waldman, L A; Goldberg, I; Greebler, P; Kelley, M D; Davis, R A; Keck, C E; Redfield, J A; Murphy,; Walker, P M

ARC-XSEC1 provides the capability of manipulating multigroup microscopic cross section data in the XS.ISO format to affect modifications of the isotopic cross section components, to collapse the energy group structure to fewer groups, and to homogenize mixtures into material and composition level data for use by the neutronics modules of the Argonne Reactor Computation (ARC) System.IBM360; FORTRAN IV; OS/360; 300K bytes with a 10,000 doubleword container (default) and 2 peripheral I/O devices.

• Research Organization: Argonne National Lab., IL (USA)
• OSTI ID: 6212608
• Report Number(s): ANL/NESC-594; ON: DE83048594
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
A CODES
COMPUTER CODES
CROSS SECTIONS
DATA PROCESSING
GROUP CONSTANTS
MULTIGROUP THEORY
NEUTRON TRANSPORT THEORY
PROCESSING
TRANSPORT THEORY