Thermal hydraulic evaluation of advanced wire-wrapped assemblies

Technical Report · Thu Jul 31 04:00:00 EDT 1975

DOI:https://doi.org/10.2172/5746185· OSTI ID:5746185

Wei, J P

The thermal-hydraulic analyses presented in this report are based on application of the subchannel concept in association with the use of bulk parameters for coolant velocity and coolant temperature within a subchannel. The interactions between subchannels are due to turbulent interchange, pressure-induced diversion crossflow, directed sweeping crossflow induced by the helical wire wrap, and transverse thermal conduction. The FULMIX-II computer program was successfully developed to perform the steady-state temperature predictions for LMFBR fuel assemblies with the reference straight-start design and the advanced wire-wrap designs. Predicted steady-state temperature profiles are presented for a typical CRBRP 217-rod wire-wrapped assembly with the selected wire-wrap designs.

• Research Organization: General Electric Co., Sunnyvale, CA (USA). Fast Breeder Reactor Dept.
• DOE Contract Number: AT03-76SF77011
• OSTI ID: 5746185
• Report Number(s): DOE/SF/77011-T3; ON: DE82004248
• Country of Publication: United States
• Language: English

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