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Core Thermal Hydraulics Design

Chapter

Abstract

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.

Keywords

Pressure Drop Fuel Assembly Control Volume Approach Direct Uncertainty Inlet Plenum 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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Copyright information

© Springer Science+Business Media, LLC 2012

Authors and Affiliations

  1. 1.Pacific Northwest National Laboratory (PNNL)RichlandUSA
  2. 2.NuScale PowerCorvallisUSA

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