1DX: A One-Dimensional Diffusion Code for Generating Effective Nuclear Cross Sections
Abstract
1DX is a multipurpose, one-dimensional (plane, cylinder, sphere) diffusion theory code for use in fast reactor analysis. The code is designed to: Compute keff 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 keff 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.
- Authors:
-
- Battelle Pacific Northwest Labs., Richland, WA (United States)
- Publication Date:
- Research Org.:
- Battelle Pacific Northwest Labs., Richland, WA (United States)
- Sponsoring Org.:
- Existing record identified as Nuclear Criticality Safety Program (NCSP) record. ALM (IS Team); US Atomic Energy Commission (AEC)
- OSTI Identifier:
- 4781436
- Report Number(s):
- BNWL-954
- NSA Number:
- NSA-23-031154
- DOE Contract Number:
- AT(45-1)-1830
- Resource Type:
- Technical Report
- Resource Relation:
- Other Information: UNCL. Orig. Receipt Date: 31-DEC-69
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 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
Citation Formats
Hardie, R. W., and Little, Jr, W. W. 1DX: A One-Dimensional Diffusion Code for Generating Effective Nuclear Cross Sections. United States: N. p., 1969.
Web. doi:10.2172/4781436.
Hardie, R. W., & Little, Jr, W. W. 1DX: A One-Dimensional Diffusion Code for Generating Effective Nuclear Cross Sections. United States. https://doi.org/10.2172/4781436
Hardie, R. W., and Little, Jr, W. W. 1969.
"1DX: A One-Dimensional Diffusion Code for Generating Effective Nuclear Cross Sections". United States. https://doi.org/10.2172/4781436. https://www.osti.gov/servlets/purl/4781436.
@article{osti_4781436,
title = {1DX: A One-Dimensional Diffusion Code for Generating Effective Nuclear Cross Sections},
author = {Hardie, R. W. and Little, Jr, W. W.},
abstractNote = {1DX is a multipurpose, one-dimensional (plane, cylinder, sphere) diffusion theory code for use in fast reactor analysis. The code is designed to: Compute keff 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 keff 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.},
doi = {10.2172/4781436},
url = {https://www.osti.gov/biblio/4781436},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sat Mar 01 00:00:00 EST 1969},
month = {Sat Mar 01 00:00:00 EST 1969}
}