LMFBR source term iodine attenuation test of bubble breakup/coalescence in LMFBR outlet plenum following large fission gas release

Technical Report · Mon Dec 01 04:00:00 EST 1975

DOI:https://doi.org/10.2172/7231204· OSTI ID:7231204

Dickinson, D. R.; Nunamaker, F. H.

Tests were performed with water in a 0.51-scale model to determine the bubble sizes and degree of contact of liquid and gas in the CRBR outlet plenum following a hypothetical large sudden release of fission gas from the fuel. The test assembly modeled the tops of six fuel subassemblies surrounding a control rod, the chimney above these, and the free space in the outlet plenum up to the suppressor plate. A known volume of gas was introduced rapidly by opening a valve from a pressurized storage reservoir. Test parameters studied were liquid flow rate (modeling 0, 10 and 50 percent CRBR flow); number of fuel subassemblies with gas release (1 and 6); volume of gas released (modeling 40 and 100 percent of end-of-life gas inventory); and speed of gas release (less than 1 sec and 8 sec). Data were obtained by direct visual observation and by high-speed color motion pictures.

• Research Organization: Hanford Engineering Development Lab., Richland, Wash. (USA)
• DOE Contract Number: EY-76-C-14-2170
• OSTI ID: 7231204
• Report Number(s): HEDL-TC-537
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATTENUATION
BREEDER REACTORS
BUBBLES
CLINCH RIVER BREEDER REACTOR
COOLING SYSTEMS
ELEMENTS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCT RELEASE
FISSION PRODUCTS
FLUIDS
FUEL ELEMENT FAILURE
GASES
HALOGENS
IODINE
ISOTOPES
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
NONMETALS
POWER REACTORS
PRIMARY COOLANT CIRCUITS
RADIOACTIVE MATERIALS
RADIOACTIVITY TRANSPORT
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SIMULATION
SODIUM COOLED REACTORS