1DX; one-dimensional diffusion fast cross section generation. [UNIVAC1108; IBM360,370; FORTRAN IV (UNIVAC1108), FORTRAN IV and BAL (IBM360,370)]

Technical Report ·

OSTI ID:6484660

Hardie, R W

1DX is a multipurpose, one-dimensional diffusion code for generating cross sections to be used in fast reactor analyses. The code is designed to - (a) compute and punch resonance shielded cross sections using data in the Russian (see reference 2) format, (b) compute and punch group-collapsed microscopic and/or macroscopic cross sections averaged over the spectrum in any specified zone, and (c) compute keff and perform criticality searches on time absorption, material concentrations, zone dimensions, and buckling using either a flux or an adjoint model.UNIVAC1108;IBM360,370; FORTRAN IV (UNIVAC1108), FORTRAN IV and BAL (IBM360,370); OS/360,370 (IBM360,370); 65K memory and 7 peripheral storage devices (UNIVAC1108), 145K and maximum of 8 storage devices (IBM360,370).

• Research Organization: Pacific Northwest Lab., Richland, WA (USA)
• OSTI ID: 6484660
• Report Number(s): ANL/NESC-374; ON: DE83048374
• Resource Relation: Other Information: 1DX uses variable dimensioning to make maximum use of existing core storage. All subscripted variables are stored in one array dimensioned to 35,000 on the UNIVAC1108. Allocation is dynamic in the IBM versions
• Country of Publication: United States
• Language: English

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
COMPUTER CODES
D CODES
NEUTRON DIFFUSION EQUATION
ONE-DIMENSIONAL CALCULATIONS
NEUTRON REACTIONS
CROSS SECTIONS
CRITICALITY
DIFFUSION
FAST REACTORS
ITERATIVE METHODS
BARYON REACTIONS
DIFFERENTIAL EQUATIONS
EPITHERMAL REACTORS
EQUATIONS
HADRON REACTIONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
REACTORS
654003* - Radiation & Shielding Physics- Neutron Interactions with Matter