Reflooding experiments with LWR-type fuel rod simulators in the QUENCH facility

Sepold, L.; Hofmann, P.; Leiling, W.; Miassoedov, A.; Piel, Daniel; Schmidt, LH; Steinbrück, M.

doi:10.1016/s0029-5493(00)00308-3

Cited by 79 publications

(10 citation statements)

References 3 publications

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“…In the framework of loss of coolant accident (LOCA) and severe fuel damage (SFD) nuclear accident research the behavior of hydrogen produced by steam oxidation of fuel rod cladding tubes was studied in a lot of experiments [1][2][3]. The coexistence of hot fuel and cooling water results in a strongly exothermic reaction between cladding and steam with the consequence of production of protons:…”

Section: Introductionmentioning

confidence: 99%

Influence of oxide layer morphology on hydrogen concentration in tin and niobium containing zirconium alloys after high temperature steam oxidation

Große

Lehmann

Steinbrück

et al. 2009

Journal of Nuclear Materials

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Section: Introductionmentioning

confidence: 99%

Influence of oxide layer morphology on hydrogen concentration in tin and niobium containing zirconium alloys after high temperature steam oxidation

Große

Lehmann

Steinbrück

et al. 2009

Journal of Nuclear Materials

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“…He analyzed boiling curve from heated rod temperature temperature's data. L. Spood et al [7] observed characteristic on temperature transient increasing at heated rod as fuel rod simulation of PWR type. W.J.…”

Section: Introductionmentioning

confidence: 99%

Experimental Study of Quenching Process During Bottom Reflooding Using “Queen” Test Section

et al. 2011

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EXPERIMENTAL STUDY OF QUENCHING PROCESS DURING BOTTOM REFLOODING USING "QUEEN" TEST SECTION.Phenomenon of quenching of hot fuels in core during bottom reflooding following loca event is investigated in order to understand the performance cooling process. the study is conducted experimentally using queen test section which allow study of rod surface temperature histories based on which the heat fluxes are estimated. the visual observation is also done to study the boiling regimes. the test variables are initial rod temperature, i.e. 400 o c, 500 o c and 600 o c, and coolant flow rate, i.e. 0,01kg/s, 0.02 kg/s and 0.04 kg/s with constant water inlet temperature of 30 o c. the results shows different heat transfer regimes such as film boiling, transition boiling, nucleate boiling and convective single phase heat transfer regimes. for specified initial rod temperature, the higher flow rate provides high rewet velocity and higher maximum heat flux, then quenching process is more effective.

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“…The reaction processes are studied e.g. by [1][2][3]. The water molecule reacts with oxygen vacancies at the gas/oxide surface.…”

Section: Introductionmentioning

confidence: 99%

“…The absorbed hydrogen temporarily affects the risk of hydrogen detonation and degrades the mechanical properties of the damaged fuel rod cladding, at least at low temperatures [7]. For the Zr-Nb alloys between 10% and 40% of the hydrogen produced according to (1) were absorbed after 15 min steam oxidation at 1,000°C depending on the niobium content and the afterwards thermal treatment [6]. In QUENCH bundle experiments, 0.8-6% of the hydrogen produced was absorbed in the residual metal [3].…”

Section: Introductionmentioning

confidence: 99%

Kinetics of Hydrogen Absorption and Release in Zirconium Alloys During Steam Oxidation

Große¹,

Steinbrueck²,

Lehmann

et al. 2008

Oxid Met

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The kinetics of hydrogen absorption during steam oxidation in Zr-Sn and Zr-Nb alloys in the temperature range of 1,000-1,400°C was investigated by neutron radiography. Hydrogen uptake can be subdivided into two steps: an initial phase and a state of equilibrium. The initial phase is controlled by the kinetics of hydrogen diffusion through the growing oxide layer. In the state of equilibrium, transport kinetics does not determine the hydrogen content of the material. An equilibrium is established between the hydrogen content of the gas environment and the metal phases. The temperature dependence of hydrogen absorption is Arrheniuslike at temperatures between 1,100 and 1,300°C.

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Reflooding experiments with LWR-type fuel rod simulators in the QUENCH facility

Cited by 79 publications

References 3 publications

Influence of oxide layer morphology on hydrogen concentration in tin and niobium containing zirconium alloys after high temperature steam oxidation

Influence of oxide layer morphology on hydrogen concentration in tin and niobium containing zirconium alloys after high temperature steam oxidation

Experimental Study of Quenching Process During Bottom Reflooding Using “Queen” Test Section

Kinetics of Hydrogen Absorption and Release in Zirconium Alloys During Steam Oxidation

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