PFR/TREAT Tests L04 and L06: irradiated versus fresh LMFBR fuel under TUCOP accident conditions

Conference · Sun Jan 01 00:00:00 EST 1984

OSTI ID:6065226

Bauer, T H; Tylka, J P; Fink, C L; Stanford, G S; Wright, A E; Herbert, R

Test L06, closely following L04 in the PFR/TREAT series, was a multi-pin simulation of a LMFBR transient under cooling/overpower (TUCOP) accident using full-length prototypic UK fast reactor fuel. In L04 the test fuel had been pre-irradiated to effect some fuel restructuring and fission gas retention. By contrast, in L06 the test fuel ws fresh. The pre-failure test fuel power and coolant flow histories in L04 were duplicated as closely as possible in L06 to make the L04/L06 pair a direct comparison of the performance of fresh versus irradiated fuel under TUCOP conditions. Identical 7-pin gridded test bundles in identically outfitted MK-3 integral flowing sodium loops also contributed to test environments in L04 and L06 that were as close as possible.

• Research Organization: Argonne National Lab., IL (USA); UKAEA Atomic Energy Establishment, Winfrith
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 6065226
• Report Number(s): CONF-841105-61; ON: DE85006188
• Resource Relation: Conference: Joint meeting of the American Nuclear Society and the Atomic Industrial Forum, Washington, DC, USA, 11 Nov 1984
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
TRANSIENT OVERPOWER ACCIDENTS
HEAT TRANSFER
HYDRAULICS
EXPERIMENTAL DATA
FLOW RATE
FUEL ELEMENT FAILURE
FUEL PINS
REACTOR SAFETY
SODIUM
TEMPERATURE GRADIENTS
VOID FRACTION
ACCIDENTS
ALKALI METALS
BREEDER REACTORS
DATA
ELEMENTS
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FUEL ELEMENTS
INFORMATION
LIQUID METAL COOLED REACTORS
MECHANICS
METALS
NUMERICAL DATA
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
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