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
• Country of Publication: United States
• Language: English

Related Subjects

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