THERMAL HYDRAULICS CALCULATION AND SAFETY ANALYSIS FOR 10MW MULTIPURPOSE RESEARCH REACTOR USING VVR-KN LOW ENRICHED FUEL
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Abstract
The PLTEMP/ANL.V4.2 and PARET/ANL.V7.5 codes were used for thermal hydraulics calculation and safety analysis of a high-power multipurpose research reactor using low enriched fuel VVR-KN. At a steady condition, the calculation results show that the maximum temperatures of fuel cladding surface and coolant were about 93.0oC and 72.0oC, respectively and the minimum Onset of Nucleate Boiling Ratio (ONBR) was approximately 1.46 when the inlet coolant temperature was 45.0oC and the coolant flow rate was 5.60 kg/s. These thermal hydraulics parameters completely met the safety requirements of the fuel supplier that the maximum temperature of the fuel cladding surface is not allowed to exceed 98oC and ONBR is higher than 1.30. For safety analysis, some accident scenarios were analyzed consisting of reactivity insert accident (RIA) and partial and total loss of coolant (LOFA) when a small break of the primary loop or station blackout occurred. At the 110% of nominal power and during accident conditions, the maximum temperature of fuel cladding was not higher than 110oC and ONBR was higher than 1.30. The obtained results are useful for the safety evaluation of the proposed core configurations using VVR-KN fuel with six cycles from initial to equilibrium cores.
Keywords
Cladding temperature, LOCA, ONB, PARET/ANL.V7.5, PLTEMP/ANL.V4.2, RIA, safety analysis, steady state, thermal hydraulics, transient/accident conditions, VVR-KN
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References
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