| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 1728844 | Annals of Nuclear Energy | 2012 | 9 Pages |
Key thermal hydraulic parameters of the 3 MW TRIGA Mark-II research reactor operating under steady-state conditions were investigated using the thermal hydraulic codes NCTRIGA, PARET and COOLOD-N2. Results of the neutronic analysis performed by 3-D Monte Carlo code MCNP4C were used in NCTRIGA and coupled output of neutronic analysis carried out by using 3-D diffusion code CITATION and 3-D Monte Carlo code MCNP4B2 were used in the PARET to study the steady-state thermal hydraulic behavior of the reactor. To benchmark the NCTRIGA, PARET and COOLOD-N2 models, data were obtained from different measurements executed by thermocouples in the instrumented fuel elements (C1 and D2) and the hottest fuel element (C4) during the steady-state operation both under forced and natural convection mode and compared with the calculation found to be quite consistent. The mass flow rates needed for input to PARET and COOLOD-N2 were taken from final safety analysis report (FSAR) for a downward forced coolant flow equivalent to 3500 gpm. For natural convection cooling of reactor, mass flow rate was generated using NCTRIGA code. The testing of the NCTRIGA, PARET and COOLOD-N2 model calculations through benchmarking the available TRIGA experimental and operational data showed that NCTRIGA, PARET and COOLOD-N2 codes can successfully be used to analyze the thermal hydraulic behavior of the reactor for the steady-state operation under both natural and forced convection mode of coolant flow to predict the safety margins. The result obtained in this investigation can be used for upgrading the current core configuration of the TRIGA reactor.
► Key thermal hydraulic parameters of the 3 MW TRIGA Mark-II research reactor were investigated under steady-state conditions. ► The thermal hydraulic codes NCTRIGA, PARET and COOLOD-N2 were employed for investigation. ► The NCTRIGA, PARET and COOLOD-N2 model calculations were benchmarked through the TRIGA experimental and operational data. ► The result obtained in this investigation can be used for upgrading the current core configuration of the TRIGA reactor.
