Pregled bibliografske jedinice broj: 713763
The Application of a Multi-Physics Toolkit to Spatial Reactor Dynamics
The Application of a Multi-Physics Toolkit to Spatial Reactor Dynamics // International Conference on Mathematics, Computational Methods & Reactor Physics. American Nuclear Society
Saratoga Springs (NY), Sjedinjene Američke Države, 2009. (predavanje, međunarodna recenzija, cjeloviti rad (in extenso), znanstveni)
CROSBI ID: 713763 Za ispravke kontaktirajte CROSBI podršku putem web obrasca
Naslov
The Application of a Multi-Physics Toolkit to Spatial Reactor Dynamics
Autori
Clifford, I. ; Jasak, Hrvoje
Vrsta, podvrsta i kategorija rada
Radovi u zbornicima skupova, cjeloviti rad (in extenso), znanstveni
Skup
International Conference on Mathematics, Computational Methods & Reactor Physics. American Nuclear Society
Mjesto i datum
Saratoga Springs (NY), Sjedinjene Američke Države, 03.05.2009. - 07.05.2009
Vrsta sudjelovanja
Predavanje
Vrsta recenzije
Međunarodna recenzija
Ključne riječi
Diffusion; Finite-Volume; Dynamics; Multi-Physics
Sažetak
Traditionally coupled field nuclear reactor analysis has been carried out using several loosely coupled solvers, each having been developed independently from the others. In the field of multi-physics, the current generation of object-oriented toolkits provides robust close coupling of multiple fields on a single framework. This paper describes the initial results obtained as part of continuing research in the use of the OpenFOAM multi-physics toolkit for reactor dynamics application development. An unstructured, three-dimensional, time-dependent multi-group diffusion code DiffusionFOAM has been developed using the OpenFOAM multi-physics toolkit as a basis. The code is based on the finite-volume methodology and uses a newly developed block-coupled sparse matrix solver for the coupled solution of the multi-group diffusion equations. A description of this code is given with particular emphasis on the newly developed block-coupled solver, along with a selection of results obtained thus far. The code has performed well, indicating that the OpenFOAM toolkit is suited to reactor dynamics applications. This work has shown that the neutronics and simplified thermal-hydraulics of a reactor may be represented and solved for using a common calculation platform, and opens up the possibility for research into robust close- coupling of neutron diffusion and thermal-fluid calculations. This work has further opened up the possibility for research in a number of other areas, including research into three-dimensional unstructured meshes for reactor dynamics applications
Izvorni jezik
Engleski
Znanstvena područja
Strojarstvo