1DB, a one-dimensional diffusion code for nuclear reactor analysis
- 1. Pacific Northwest Lab., Richland, WA (United States)
Description
1DB is a multipurpose, one-dimensional (plane, cylinder, sphere) diffusion theory code for use in reactor analysis. The code is designed to do the following: To compute keff and perform criticality searches on time absorption, reactor composition, reactor dimensions, and buckling by means of either a flux or an adjoint model; to compute collapsed microscopic and macroscopic cross sections averaged over the spectrum in any specified zone; to compute resonance-shielded cross sections using data in the shielding factor formnd to compute isotopic burnup using decay chains specified by the user. All programming is in FORTRAN. Because variable dimensioning is employed, no simple restrictions on problem complexity can be stated. The number of spatial mesh points, energy groups, upscattering terms, etc. is limited only by the available memory. The source file contains about 3000 cards. 4 refs
Availability note (English)
MF available from INIS under the Report Number; OSTI as DE92003020; NTIS; INIS; US Govt. Printing Office Dep.
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 102 p.
- Report number
- WHC-EP--0435
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23031731
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Computer Program Description
- Descriptors DEI
- BURNUP; COMPUTER PROGRAM DOCUMENTATION; CROSS SECTIONS; DIFFUSION; MATHEMATICAL MODELS; NEUTRON FLUX; NUMBER CODES; ONE-DIMENSIONAL CALCULATIONS; REACTOR PHYSICS; SHIELDING
- Descriptors DEC
- COMPUTER CODES; RADIATION FLUX
Optional Information
- Contract/Grant/Project number
- Contract AC06-87RL10930
- Funding organization
- USDOE, Washington, DC (United States).