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Inter-subassembly heat transfer of sodium cooled fast reactors: Validation of the NETFLOW code

2007; Elsevier BV; Volume: 237; Issue: 19 Linguagem: Inglês

10.1016/j.nucengdes.2007.03.023

1872-759X

Hiroyasu Mochizuki,

Nuclear Materials and Properties

This paper describes the prediction of temperature at the exit of subassemblies of a sodium cooled fast reactor using the NETFLOW code. Until present time, this plant dynamics calculation code is expected as a tool of nuclear education, and has been validated using data obtained at facilities or reactors cooled with water or sodium. A natural circulation test was conducted in the experimental fast reactor 'Joyo' with a 100 MW irradiation core. Also a turbine trip test was conducted in the prototype fast breeder reactor 'Monju'. These tests were chosen to validate a model to calculate inter-subassembly heat transfer consisting of heat conduction and heat transfer by inter-wrapper flow. Based on the calculation for the natural circulation test in primary and secondary loops of 'Joyo', the model to calculate the heat transfer in radial direction of the inter-subassemblies simulated reasonable sodium temperature behaviors at the exit of subassemblies. Good agreement was also obtained in prediction of temperatures at the exit of the 'Monju' subassemblies. Through these validations, it was shown that the one-dimensional plant dynamics code NETFLOW could trace temperatures at the exit of the subassemblies of fast reactors with the inter-subassembly heat transfer model.