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- Bechta, Sevostian, et al.
(author)
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Interaction between molten corium UO2+X-ZrO2-FeO y and VVER vessel steel
- 2009
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In: Proceeding of International Conference on Advances in Nuclear Power Plants, ICAPP 2008. - : Curran Associates, Inc.. - 9781605607870 ; , s. 210-218
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Conference paper (peer-reviewed)abstract
- In case of an in-vessel corium retention (1VR) the deterioration of vessel steel properties can be caused both by the steel melting and by its physicochemical interaction with corium. The interaction behavior has been studied in the medium-scale experiments with a prototypic corium within the METCOR project. The resulting experimental data give an insight into the steel corrosion during its interaction with U02+x- Zr02- FeOy melt in air and steam. It has been observed that the corrosion rate is almost the same in air and steam atmosphere; if the temperature on the interaction interface increases beyond a certain level, corrosion intensifies, which is explained by the formation of liquid phases in the interaction zone. The available experimental data have been used for developing a correlation of corrosion rate versus temperature and heat flux.
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2. |
- Journeau, C., et al.
(author)
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European Research on the Corium issues within the SARNET network of excellence
- 2008
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In: International Conference on Advances in Nuclear Power Plants, ICAPP 2008. - 9781605607870 ; , s. 1172-1181
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Conference paper (peer-reviewed)abstract
- Within SARNET, the corium topic covers all the behaviors of corium from early phase of core degradation to in or ex-vessel corium recovery with the exception of corium interaction with water, direct containment heating and fission product release. The corium topic regroups in three work packages the critical mass of competence required to improve significantly the corium behavior knowledge. The spirit of the SARNET networking is to share the knowledge, the facilities and the simulation tools for severe accidents, so to reach a better efficiency and to rationalize the R&D effort at European level. Extensive benchmarking has been launched in most of the areas of research. These benchmarks were mainly dedicated to the recalculation of experiments, while, in the next periods, a larger focus will be given to integral experiments or reactor applications. Eventually, all the knowledge will be accumulated in the ASTEC severe accident simulation code through physical model improvements and extension of validation database. This paper summarizes the progress that has been achieved in the frame of the networking activities. A special focus is placed on the melt pool and debris coolability and corium-concrete interaction, in which, the effects due to multidimensional geometries and heterogeneities has been shown, during SARNET, to play a crucial role and for which further research is still needed.
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3. |
- Kudinov, Pavel, et al.
(author)
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An experimental study on debris formation with corium simulant materials
- 2008
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In: International Conference on Advances in Nuclear Power Plants, ICAPP 2008. - 9781605607870 ; , s. 1191-1199
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Conference paper (peer-reviewed)abstract
- Characteristics of corium debris beds formed in a severe coremelt accident are studied in DEFOR-S experiments, in which binary-oxidic simulant-material melts are discharged into a water pool. Water subcooling and pool depth are found to significantly influence the fragment morphology and agglomeration. The DEFOR-S data to date are indicative of the effect of melt composition, notably eutectic vs. non-eutectic. Synthesis of the DEFOR-S observations with respect to debris fragment's shape and surface roughness suggest the governing role of competitive mechanism: drop breakup, freezing and solid fracture.
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5. |
- Starflinger, J., et al.
(author)
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Progress within the European project : "High performance light water reactor phase 2" (HPLWR Phase 2)
- 2008
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In: International Conference on Advances in Nuclear Power Plants, ICAPP 2008. - 9781605607870 ; , s. 649-659
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Conference paper (peer-reviewed)abstract
- The High Performance Light Water Reactor (HPLWR) is a Light Water Reactor (LWR) operating at supercritical pressure (25MPa). It belongs to the six reactors currently being investigated under the framework of the Generation IV International Forum. In Europe, investigations on the HPLWR have been integrated into a joint research project, called High Performance Light Water Reactor Phase 2 (HPLWR Phase 2), which is co-funded by the European Commission. Within 42 months, ten partners from eight European countries working on critical scientific issues shall show the feasibility of the HPLWR concept. The final goal is to assess the future potential of this reactor in the electricity market. Within the first year of the project, mainly design tasks of the reactor core, the pressure vessel and its internals have been carried out and codes were adapted for supercritical fluid. Material oxidation experiments were performed and heat transfer was investigated numerically.
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6. |
- Yakush, S., et al.
(author)
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Modeling of Two-Phase Natural Convection Flows in a Water Pool with a Decay-Heated Debris Bed
- 2008
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In: Proceedings of International Congress on Advances in Nuclear Power Plants (ICAPP 2008). - 9781605607870
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Conference paper (peer-reviewed)abstract
- Coolability of a debris bed in a water pool is studied numerically with the emphasis on the effects of natural convection flows driven by vapor release in the porous bed. A multifluid computer code DECOSIM is developed and applied to the simulation of liquid-vapor flows in the saturated conditions relevant to the long transient of the debris bed formation and coolability problems. Numerical calculations carried out reveal the influence of the debris bed shape on the structure of natural circulation flows in the water pool, as well as on the void fraction distributions inside the debris bed. The effect of large scale flow structures in the pool on transport of debris particles is demonstrated. It is shown that the vortical flow can capture the smaller particle which may result in considerable spreading of the sedimented debris over the pool floor.
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