Characteristics of corium debris bed generated in large-scale fuel-coolant interaction experiments

Magallon, D.

doi:10.1016/j.nucengdes.2006.03.038

Cited by 153 publications

(29 citation statements)

References 14 publications

(13 reference statements)

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“…Past work, [13][14][15][16] TROI tests, and Fig. 10 show that the particle size is highly dependent on the material type; the large particle sizes of alumina, zirconia, 70:30 corium, and 80:20 corium seem to be 10-30, -10, -6, and -6 mm, respectively.…”

Section: Evaluation Of a Heat Loss By Using A Single-particle Heat Trmentioning

confidence: 85%

“…The formation of corium debris as a result of a fuel coolant interaction was experimentally analyzed in the FARO and KROTOS facilities. 13) The debris in FARO formed a cake in contact with the bottom and with overlaying fragments, as in TMI (hard layer and loose debris, respectively). The loose debris meant that the particle size was in the range of 3.0-4.8 mm in all the tests where no special event occurred.…”

Section: Analyses Of a Particle Size Distribution For The Troi Tmentioning

confidence: 99%

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A Mechanism for the Suppression of a Steam Explosion in Real Core Melt and Water Interactions

Park

Kim

Min

et al. 2010

Journal of Nuclear Science and Technology

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TROI experiments1) have been performed to reveal unsolved issues of a steam explosion by using real core material at the Korea Atomic Energy Research Institute (KAERI). One of the findings from the TROI experiments is that the results of a fuel coolant interaction (FCI) are strongly dependent on the composition of corium, which is composed of UO 2 , ZrO 2 , Zr, and steel. The TEXAS-V simulation for the TROI experiments indicated that a relatively low void fraction seems to have resulted in a strong steam explosion, and the low-voided mixture seems to have been induced by large-sized particles. The particle sizes in the nonexplosive TROI tests were analyzed because the explosive tests do not represent the particles during mixing. The analysis of particle sizes indicated that the debris size reflected the material difference, and the order of the particle size for each melt material was the same as that in the TEXAS-V simulation. The TEXAS-V calculation for the alumina/water system indicated that thermal conductivity is also related to the material effect on the FCI result. A heat loss evaluation using a single-sphere, filmboiling model showed that reliable values for thermal conductivity and particle size provide a reasonable estimation for the FCI result. The steam explosion in corium/water interactions is suppressed by a smaller particle size and an induced larger heat loss during mixing.

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Section: Evaluation Of a Heat Loss By Using A Single-particle Heat Trmentioning

confidence: 85%

Section: Analyses Of a Particle Size Distribution For The Troi Tmentioning

confidence: 99%

A Mechanism for the Suppression of a Steam Explosion in Real Core Melt and Water Interactions

Park

Kim

Min

et al. 2010

Journal of Nuclear Science and Technology

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show abstract

“…It is true even for small particles arising behind the shock wave [68][69][70]. We assume also that thickness of steam layer at the particle surface is much greater than the radiation wavelength.…”

Section: Cooling and Solidification Of Corium Particlesmentioning

confidence: 99%

Steam explosion in nuclear reactors: Droplets of molten steel vs core melt droplets

Dombrovsky

2017

International Journal of Heat and Mass Transfer

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“…The breakup of melt jets penetrating into water pools has been investigated experimentally with corium melt in the FARO experiments [24], using jets of 5-10 cm diameter with about 5 m/s initial penetration velocity into 1-2 m deep water. Up to 177 kg melt mass was released, mostly into saturated water under different system pressures from 5 -0.2 MPa.…”

Section: Experiments On Formation Of Particulate Debris In Water Poolmentioning

confidence: 99%

Late Containment Failure

2012

Nuclear Safety in Light Water Reactors

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Characteristics of corium debris bed generated in large-scale fuel-coolant interaction experiments

Cited by 153 publications

References 14 publications

A Mechanism for the Suppression of a Steam Explosion in Real Core Melt and Water Interactions

A Mechanism for the Suppression of a Steam Explosion in Real Core Melt and Water Interactions

Steam explosion in nuclear reactors: Droplets of molten steel vs core melt droplets

Late Containment Failure

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