Compilation of data from EBR-II natural-circulation-test procedure EX-140, Section IV, Addendum 8

Technical Report · Wed Apr 30 20:00:00 EDT 1980

DOI:https://doi.org/10.2172/711589· OSTI ID:711589

Gillette, J L; Sullivan, J E; Singer, R M; Tokar, J V; Dean, E M

The transition from forced to natural-circulation flow of primary coolant after the loss of primary pumping power with concomitant reactor scram has been investigated in Experimental Breeder Reactor No. II. Before the loss-of-flow transient, the reactor was operated at 22.3 MWt (37.2% of the normal full-power value) and at 39.3% of normal full flow. The effects of inter- and intrasubassembly heat transfer in reducing temperature gradients in the primary system were again observed. Consequences of the delayed secondary-system flow coastdown on the natural-circulation flows and temperatures in the primary system were also measured. Data were collected by the EBR-II data-acquisition system from the usual plant process instrumentation and instrumented subassembly XX08. The method used to correct the data for signal offsets is discussed. The corrected test data are presented graphically.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: W-31109-ENG-38; NONE
• OSTI ID: 711589
• Report Number(s): ANL/EBR--112; 194310
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
AFTER-HEAT
AFTER-HEAT REMOVAL
DATA COMPILATION
EBR-2 REACTOR
HEAT TRANSFER
LOSS OF FLOW
NATURAL CONVECTION
REACTOR OPERATION
REACTOR SAFETY
TEMPERATURE GRADIENTS