1DX: A One-Dimensional Diffusion Code for Generating Effective Nuclear Cross Sections

Technical Report · Sat Mar 01 00:00:00 EST 1969

DOI:https://doi.org/10.2172/4781436· OSTI ID:4781436

Hardie, R. W. ^[1]; Little, Jr, W. W. ^[1]

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1. Battelle Pacific Northwest Labs., Richland, WA (United States)

1DX is a multipurpose, one-dimensional (plane, cylinder, sphere) diffusion theory code for use in fast reactor analysis. The code is designed to: Compute k_eff and perform criticality searches on time absorption (α), reactor composition, reactor dimensions, and buckling by means of either a flux or an adjoint model; Compute and punch collapsed microscopic and macroscopic cross sections averaged over the spectrum in any specified zone; Compute and punch resonance shielded cross sections using data in the "Russian" format. All programming is in FORTRAN-IV. Since variable dimensioning is employed, no simple restrictions on problem complexity can be stated. In a 65K memory, 100-group problems are feasible for a moderate number of mesh intervals (~30). A representative 26-group k_eff calculation with 30 spatial intervals using data in the "Russian" format requires about 40 seconds on a UNIVAC 1108. If the cross section data is in the "DTF" format, the same problem would require about 5 seconds.

• Research Organization: Battelle Pacific Northwest Labs., Richland, WA (United States)
• Sponsoring Organization: Existing record identified as Nuclear Criticality Safety Program (NCSP) record. ALM (IS Team); US Atomic Energy Commission (AEC)
• DOE Contract Number: AT(45-1)-1830
• NSA Number: NSA-23-031154
• OSTI ID: 4781436
• Report Number(s): BNWL-954
• Resource Relation: Other Information: UNCL. Orig. Receipt Date: 31-DEC-69
• Country of Publication: United States
• Language: English

Related Subjects

97 MATHEMATICS AND COMPUTING
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
COMPUTERS
CRITICALITY
CROSS SECTIONS
DIGITAL SYSTEMS
FAST NEUTRONS
FAST REACTORS
FORTRAN
PROGRAMMING
REACTIVITY
REACTORS
UNIVAC
Nuclear Criticality Safety Program (NCSP)
Criticality
Cross Sections
Digital Systems
Fast Neutrons
Fast Reactors
Fortran
Programming
Reactivity
DTF Format
Russian Format
1DX
Diffusion Code
Nuclear Cross Sections
N38110* -Power Reactor Development-Kinetics & Dynamics