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Coolant mixing in LMFBR rod bundles and outlet plenum mixing transients. Final report

Technical Report ·
DOI:https://doi.org/10.2172/6006053· OSTI ID:6006053
This project principally undertook the investigation of the thermal hydraulic performance of wire wrapped fuel bundles of LMFBR configuration. Results obtained included phenomenological models for friction factors, flow split and mixing characteristics; correlations for predicting these characteristics suitable for insertion in design codes; numerical codes for analyzing bundle behavior both of the lumped subchannel and distributed parameter categories and experimental techniques for pressure velocity, flow split, salt conductivity and temperature measurement in water cooled mockups of bundles and subchannels. Flow regimes investigated included laminar, transition and turbulent flow under forced convection and mixed convection conditions. Forced convections conditions were emphasized. Continuing efforts are underway at MIT to complete the investigation of the mixed convection regime initiated here. A number of investigations on outlet plenum behavior were also made. The reports of these investigations are identified.
Research Organization:
Massachusetts Inst. of Tech., Cambridge (USA). Dept. of Nuclear Engineering
DOE Contract Number:
AC02-76ET37240
OSTI ID:
6006053
Report Number(s):
DOE/ET/37240-109-PR; ON: DE85010336
Country of Publication:
United States
Language:
English