Simulant material pour stream breakup tests and model implications

Technical Report · Sat Aug 01 04:00:00 EDT 1987

DOI:https://doi.org/10.2172/713860· OSTI ID:713860

Gabor, J D; Spencer, B W; Cassulo, J C

An understanding of the mechanisms of pour stream breakup and quench in a liquid coolant is required in analyses of reactor accident scenarios involving liquefaction of core materials and their downward migration into coolant in the vessel lower head region. If the molten core materials are quenched, a bed of solid particles is formed, and analysis would then assess the coolability of this bed. On the other hand, if the pour stream has not solidified as it passes through coolant, jet impingement heat transfer and attack by a melt layer must be considered. The purpose of this investigation was to visualize processes important to the jet breakup, quench, and solidification under a broad range of conditions to evaluate models for possible reactor-scale application. Previous basic research has primarily been with small diameter jets (in the order of 1 mm) and with low density fluids (water, air, and organic liquids). Reactor safety analysis is concerned with large diameter pour streams (>20 mm) of high density materials (uranium oxides and alloys) in coolant. In addition, consideration must be given to the effect of phase change of both the pour stream material (freezing) and the reactor coolant (boiling) on the breakup of the stream. However, previous investigations have contributed significantly to the understanding of the mechanisms of jet breakup and provide considerable information useful to safety assessments. These are discussed.

• Research Organization: Argonne National Lab., IL (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 713860
• Report Number(s): ANL-IFR--77; ON: TI87028767
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
CALCULATION METHODS
CORIUM
LMFBR TYPE REACTORS
MOLTEN METAL-WATER REACTIONS
QUENCHING
REACTOR ACCIDENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
RESEARCH PROGRAMS