ORNL rod-bundle heat-transfer test data. Volume 2. Thermal-Hydraulic Test Facility experimental data report for test 3. 03. 6AR - transient film boiling in upflow

Technical Report · Thu Apr 01 00:00:00 EST 1982

DOI:https://doi.org/10.2172/5274301· OSTI ID:5274301

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

Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) Test 3.03.6AR. This test was conducted by members of the ORNL Pressurized-Water-Reactor (PWR) Blowdown Heat Transfer (BDHT) Separate-Effects Program on May 21, 1980. Objective was to investigate heat transfer phenomena believed to occur in PWRs during accidents, including small and large break loss-of-coolant accidents. Test 3.03.6AR was conducted to obtain transient film boiling data in rod bundle geometry under reactor accident-type conditions. The primary purpose of this report is to make the reduced instrument responses for THTF Test 3.03.6AR available. Included in the report 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)
• Sponsoring Organization: US Nuclear Regulatory Commisssion; USDOE
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5274301
• Report Number(s): NUREG/CR-2525-Vol.2; ORNL/NUREG/TM-407/V2; ON: DE82013652; TRN: 82-016019
• Resource Relation: Other Information: Portions of document are illegible
• Country of Publication: United States
• Language: English

Related Subjects

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LOSS OF COOLANT
HEAT TRANSFER
PWR TYPE REACTORS
BLOWDOWN
FILM BOILING
ROD BUNDLES
TEST FACILITIES
TRANSIENTS
ACCIDENTS
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Light-Water Moderated
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