Abstract
VTT maintains and further developes a comprehensive safety analysis code system ranging from the basic neutronic libraries to 3D transient analysis and fuel behaviour analysis codes. Some of the computer codes have been developed at VTT, others have been acquired from internationally recognized sources. The code system is based on various types of couplings between the relevant physival phenomena.
The main tools for analyses of reactor transients are presently the 3D reactor dynamics code HEXTRAN for cores with a hexagonal fuel assembly geometry and TRAB-3D for cores with a quadratic fuel assembly geometry. HEXTRAN has been applied to safety analyses of VVER-type reactors since early 1990’s. TRAB-3D is the latest addition to the code system, and has been applied to BWR and PWR analyses in recent years.
The results from the 3D analysis can be used as boundary conditions for more detailed fuel rod analysis. For this purpose a general flow model GENFLO, developed at VTT, has been coupled with USNRC’s FRAPTRAN fuel accident behaviour model. FRAPTRAN/GENFLO is quite a promising tool that can handle flow situations that are far too complicated for the models that are usually seen with fuel codes.
The main tools for analyses of reactor transients are presently the 3D reactor dynamics code HEXTRAN for cores with a hexagonal fuel assembly geometry and TRAB-3D for cores with a quadratic fuel assembly geometry. HEXTRAN has been applied to safety analyses of VVER-type reactors since early 1990’s. TRAB-3D is the latest addition to the code system, and has been applied to BWR and PWR analyses in recent years.
The results from the 3D analysis can be used as boundary conditions for more detailed fuel rod analysis. For this purpose a general flow model GENFLO, developed at VTT, has been coupled with USNRC’s FRAPTRAN fuel accident behaviour model. FRAPTRAN/GENFLO is quite a promising tool that can handle flow situations that are far too complicated for the models that are usually seen with fuel codes.
| Original language | English |
|---|---|
| Title of host publication | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications |
| Publisher | American Nuclear Society (ANS) |
| Number of pages | 12 |
| Publication status | Published - 2005 |
| MoE publication type | A4 Article in a conference publication |
| Event | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications Meeting, M&C 2005: 21st biennial topical meeting of the Mathematics and Computation Division of the American Nuclear Society (ANS) - Avignon, France Duration: 12 Sept 2005 → 15 Sept 2005 |
Conference
| Conference | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications Meeting, M&C 2005 |
|---|---|
| Country/Territory | France |
| City | Avignon |
| Period | 12/09/05 → 15/09/05 |