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- W2188496291 abstract "The Research Reactor Laboratory has been equipped with the thermal-hydraulic codes PLTEMP, NATCON and PARET to assess the safety issues of the GRR-1 reactor core conversion to Low Enriched Uranium (LEU) fuel. The codes are used to carry out both steady- state and transient analyses of safety margins and limits. The steady-state analysis is made for both forced and natural convection cooling. The transient analysis is made for assessing relevant accident sequences, including reactivity accidents and loss-of-flow accidents. The results of the simulations show that LEU fuel promotes reactor safety, because of the enhancement of the reactor feedback mechanisms." @default.
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- W2188496291 modified "2023-09-24" @default.
- W2188496291 title "Thermal-hydraulic Calculations for the GRR-1 Research Reactor Core Conversion to Low Enriched Uranium Fuel" @default.
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