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

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

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Abstract

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.

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

Publication Date:: 1984-01-01

Research Org.:: Argonne National Lab., IL (USA); UKAEA Atomic Energy Establishment, Winfrith

OSTI Identifier:: 6065226

Report Number(s):: CONF-841105-61
ON: DE85006188

DOE Contract Number:: W-31-109-ENG-38

Resource Type:: Conference

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

Subject:: 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, Breeding

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                    Bauer, T H, Tylka, J P, Fink, C L, Stanford, G S, Wright, A E, and Herbert, R. PFR/TREAT Tests L04 and L06: irradiated versus fresh LMFBR fuel under TUCOP accident conditions.  United States: N. p., 1984. 
        Web.

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                    Bauer, T H, Tylka, J P, Fink, C L, Stanford, G S, Wright, A E, & Herbert, R. PFR/TREAT Tests L04 and L06: irradiated versus fresh LMFBR fuel under TUCOP accident conditions.  United States.

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                    Bauer, T H, Tylka, J P, Fink, C L, Stanford, G S, Wright, A E, and Herbert, R. Sun .  
        "PFR/TREAT Tests L04 and L06: irradiated versus fresh LMFBR fuel under TUCOP accident conditions".  United States.  https://www.osti.gov/servlets/purl/6065226.

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@article{osti_6065226,

  title        = {PFR/TREAT Tests L04 and L06: irradiated versus fresh LMFBR fuel under TUCOP accident conditions},

  author       = {Bauer, T H and Tylka, J P and Fink, C L and Stanford, G S and Wright, A E and Herbert, R},

  abstractNote = {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.},

  doi          = {},

  url          = {https://www.osti.gov/biblio/6065226},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {1984},

  month        = {1}

}

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