TRIBU, a 2-dimensional triangular mesh diffusion, burnup, and fuel management program
Abstract
From 1973 annual meeting of the Belgian section of the A. N. S.; Mol, Belgium (14 Jun 1973). The program TRIBU (TRIangular miesh with BUrnup) is designed for the detailed fuel cycle analyses of fast and thermal reactors with hexagonal assemblies. The triangular grid used for the diffusion and the depletion calculations corresponds to mesh sizes equal to the side, to half the side or to one third of the side of the fuel assemblies; the isotopic compositions are computed at each point of this grid (7, 19 or 37 points/ assembly), and the flux distributions are obtained taking into account different isotopic compositions in each sixth of the assemblies, and different axial bucklings per assembly. To the burnup chains (/sup 232/Th-/sup 234/U and /sup 235/U--/sup 236/U, /sup 238/U--/sup 242/Pu) cor respond two separate sets of fission products (rapidly saturating, slowly saturating' non-saturating) as well as /sup 135/Xe, /sup 149/Sm and /sup 241/Am production. The depletion of burnable poisons (boron and samarium) is also computed. (auth)
- Authors:
- Publication Date:
- Research Org.:
- Centre d'Etude de l'Energie Nucleaire, Mol (Belgium); Societe Belge pour l'Industrie Nucleaire, Brussels
- OSTI Identifier:
- 4356043
- Report Number(s):
- INIS-mf-832
- NSA Number:
- NSA-29-020246
- Resource Type:
- Technical Report
- Resource Relation:
- Conference: 1973 annual meeting of the Belgian section of the A.N.S., Mol, Belgium, 14 Jun 1973; Other Information: Orig. Receipt Date: 30-JUN-74
- Country of Publication:
- Belgium
- Language:
- English
- Subject:
- N79100* -Reactors-Reactor Theory & Calculation; *COMPUTER CODES- T CODES; *FAST REACTORS- FUEL MANAGEMENT; *FUEL MANAGEMENT- COMPUTER CALCULATIONS; *THERMAL REACTORS- FUEL MANAGEMENT; BURNUP; FUEL ASSEMBLIES; FUEL CYCLE; HEXAGONAL CONFIGURATION
Citation Formats
Minsart, G, Peperstraete, G, Billaux, M, and Delabaye, M. TRIBU, a 2-dimensional triangular mesh diffusion, burnup, and fuel management program. Belgium: N. p., 1973.
Web.
Minsart, G, Peperstraete, G, Billaux, M, & Delabaye, M. TRIBU, a 2-dimensional triangular mesh diffusion, burnup, and fuel management program. Belgium.
Minsart, G, Peperstraete, G, Billaux, M, and Delabaye, M. 1973.
"TRIBU, a 2-dimensional triangular mesh diffusion, burnup, and fuel management program". Belgium.
@article{osti_4356043,
title = {TRIBU, a 2-dimensional triangular mesh diffusion, burnup, and fuel management program},
author = {Minsart, G and Peperstraete, G and Billaux, M and Delabaye, M},
abstractNote = {From 1973 annual meeting of the Belgian section of the A. N. S.; Mol, Belgium (14 Jun 1973). The program TRIBU (TRIangular miesh with BUrnup) is designed for the detailed fuel cycle analyses of fast and thermal reactors with hexagonal assemblies. The triangular grid used for the diffusion and the depletion calculations corresponds to mesh sizes equal to the side, to half the side or to one third of the side of the fuel assemblies; the isotopic compositions are computed at each point of this grid (7, 19 or 37 points/ assembly), and the flux distributions are obtained taking into account different isotopic compositions in each sixth of the assemblies, and different axial bucklings per assembly. To the burnup chains (/sup 232/Th-/sup 234/U and /sup 235/U--/sup 236/U, /sup 238/U--/sup 242/Pu) cor respond two separate sets of fission products (rapidly saturating, slowly saturating' non-saturating) as well as /sup 135/Xe, /sup 149/Sm and /sup 241/Am production. The depletion of burnable poisons (boron and samarium) is also computed. (auth)},
doi = {},
url = {https://www.osti.gov/biblio/4356043},
journal = {},
number = ,
volume = ,
place = {Belgium},
year = {Mon Jan 01 00:00:00 EST 1973},
month = {Mon Jan 01 00:00:00 EST 1973}
}