Compilation of data from EBR-II natural-circulation-test procedure EX-140, Section IV, Addendum 7C

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

DOI:https://doi.org/10.2172/711588· OSTI ID:711588

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 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 22.0 MWt (36.7% of the normal full-power value) and at 39.0% of normal full flow. All electrical power to the primary pumping system was terminated, causing the flow rate of the primary-system coolant to coast down. As the flow rate coasted down, the low-flow trip setting caused the reactor to scram. The transition from forced to natural-circulation flow was observed to be smooth, and the coolant temperatures throughout the reactor were observed to remain lower than the corresponding values at full-power operating conditions. Data were collected by the EBR-II data-acquisition system from the usual plant process instrumentation and instrumented subassembly XX08.

• Research Organization: Argonne National Lab., IL (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: W-31109-ENG-38; NONE
• OSTI ID: 711588
• Report Number(s): ANL/EBR--111; 194308
• 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
EBR-2 REACTOR
HEAT TRANSFER
HYDRAULICS
LOSS OF FLOW
NATURAL CONVECTION
REACTOR SAFETY
TEMPERATURE GRADIENTS