ORNL rod-bundle heat-transfer test data. Volume 7. Thermal-Hydraulic Test Facility experimental data report for test series 3. 07. 9 - steady-state film boiling in upflow

Technical Report · Sat May 01 00:00:00 EDT 1982

DOI:https://doi.org/10.2172/5274298· OSTI ID:5274298

Mullins, C. B.; Felde, D. K.; Sutton, A. G.; Gould, S. S.; Morris, D. G.; Robinson, J. J.

Thermal-Hydraulic Test Facility (THTF) test series 3.07.9 was conducted by members of the Oak Ridge National Laboratory Pressurized-Water Reactor (ORNL-PWR) Blowdown Heat Transfer (BDHT) Separate-Effects Program on September 11, September 18, and October 1, 1980. The objective of the program is to investigate heat transfer phenomena believed to occur in PWRs during accidents, including small- and large-break loss-of-coolant accidents. Test series 3.07.9 was designed to provide steady-state film boiling data in rod bundle geometry under reactor accident-type conditions. This report presents the reduced instrument responses for THTF test series 3.07.9. Also included are uncertainties in the instrument responses, calculated mass flows, and calculated rod powers.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5274298
• Report Number(s): NUREG/CR-2525-Vol.7; ORNL/NUREG/TM-407-Vol.7; ON: DE82014871; TRN: 82-016021
• Resource Relation: Other Information: Portions of document are illegible
• Country of Publication: United States
• Language: English

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FUEL ELEMENT CLUSTERS
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LOSS OF COOLANT
COOLANT LOOPS
EXPERIMENTAL DATA
FILM BOILING
FLUID FLOW
FUEL RODS
ACCIDENTS
BOILING
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220900* - Nuclear Reactor Technology- Reactor Safety
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Light-Water Moderated
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