| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 297693 | Nuclear Engineering and Design | 2010 | 13 Pages |
In this study, a new and innovative method is introduced for analyzing neutronic and thermal-hydraulic calculation. For this aim, VVR-S research reactor was selected, and the calculation procedure was performed for it. WIMS, CITATION and COBRA-EN codes were used for investigation. Calculation model consists of two sub-models: neutronic and thermo-hydraulic. The neutronic model uses WIMS and CITATION codes for neutronic simulation of the reactor core and calculating flux and power distribution over it. WIMS code simulates the fuel assemblies and CITATION models the core. The thermal-hydraulic model uses COBRA-EN code for performing the relative calculation. In this study, FORTRAN 90 program is used for linking two sub-models and performing the calculation. The proposed procedure is performed for VVR-S analysis and finally, the obtained results are compared with the experimental results that show good agreement with it.
Research highlights▶ Reactor behavior affects from reciprocal effects between neutronic and thermo-hydraulic. ▶ Reliable reactor analysis requires coupling of neutronic and thermal-hydraulic calculation. ▶ Iterative process can be used to perform neutronic and thermal-hydraulic calculation.
