In the previous chapter we explored the methodology for determining the temperature field for a single fuel pin. Since a typical fast reactor core comprises several thousand fuel pins clustered in groups of several hundred pins per assembly, a complete thermal-hydraulic analysis requires knowledge of coolant distributions and pressure losses throughout the core. This chapter will address these determinations.
CITATION STYLE
Waltar, A., & Todd, D. (2013). Core thermal hydraulics design. In Fast Spectrum Reactors (Vol. 9781441995728, pp. 263–298). Springer US. https://doi.org/10.1007/978-1-4419-9572-8_10
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