Treat sodium loop experiments on performance of unbonded, unirradiated EBR-II Mark I fuel elements

Dickerman, C.E.; Willis, F.L.; Smith, R.R.; Henault, P.B.; Purviance, R.; Boland, Jean-François; DeVolpi, A.; Noland, R.A.; Regis, J.P.; Cohen, Adam B.; Walter, Charles

doi:10.1016/0029-5493(70)90052-x

Cited by 4 publications

(1 citation statement)

References 6 publications

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“…Two tests were run in TREAT using the Mark I integral sodium loop with flowing sodium coolant. 67 " 69 The single element in each test was surrounded by six dummy elements at the same element spacing used in EBR-II. No thermal neutron filter was used, but the axial power was shaped by absorbers.…”

Section: Ebr-ii Metal Fuel Testsmentioning

confidence: 99%

Experience related to the safety of advanced LMFBR fuel elements

Kerrisk¹

1975

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Section: Ebr-ii Metal Fuel Testsmentioning

confidence: 99%

Experience related to the safety of advanced LMFBR fuel elements

Kerrisk¹

1975

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Power pulse meltdown experiments performed in the mark I TREAT sodium loop on clusters of 7 EBR-II Mark I type pins

Dickerman

Robinson

Purviance

et al. 1970

Nuclear Engineering and Design

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A review of inherent safety characteristics of metal alloy sodium-cooled fast reactor fuel against postulated accidents

Sofu

2015

Nuclear Engineering and Technology

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a b s t r a c tThe thermal, mechanical, and neutronic performance of the metal alloy fast reactor fuel design complements the safety advantages of the liquid metal cooling and the pool-type primary system. Together, these features provide large safety margins in both normal operating modes and for a wide range of postulated accidents. In particular, they maximize the measures of safety associated with inherent reactor response to unprotected, doublefault accidents, and to minimize risk to the public and plant investment. High thermal conductivity and high gap conductance play the most significant role in safety advantages of the metallic fuel, resulting in a flatter radial temperature profile within the pin and much lower normal operation and transient temperatures in comparison to oxide fuel. Despite the big difference in melting point, both oxide and metal fuels have a relatively similar margin to melting during postulated accidents. When the metal fuel cladding fails, it typically occurs below the coolant boiling point and the damaged fuel pins remain coolable. Metal fuel is compatible with sodium coolant, eliminating the potential of energetic fuelecoolant reactions and flow blockages. All these, and the low retained heat leading to a longer grace period for operator action, are significant contributing factors to the inherently benign response of metallic fuel to postulated accidents. This paper summarizes the past analytical and experimental results obtained in past sodium-cooled fast reactor safety programs in the United States, and presents an overview of fuel safety performance as observed in laboratory and in-pile tests.

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Treat sodium loop experiments on performance of unbonded, unirradiated EBR-II Mark I fuel elements

Cited by 4 publications

References 6 publications

Experience related to the safety of advanced LMFBR fuel elements

Experience related to the safety of advanced LMFBR fuel elements

Power pulse meltdown experiments performed in the mark I TREAT sodium loop on clusters of 7 EBR-II Mark I type pins

A review of inherent safety characteristics of metal alloy sodium-cooled fast reactor fuel against postulated accidents

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