Modeling of chemical interactions of fuel rod materials at high temperatures II. Investigation of downward relocation of molten materials
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Abstract
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Research context
OpenAlex topics: Nuclear Materials and Properties · High Temperature Alloys and Creep · Nuclear reactor physics and engineering
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References (16)
Show source-provided references
1. In-Vessel Core Degradation in LWR Severe Accidents
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5. Test Results of Experiment CORA W1
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7. Modellierung des Experiments CORA und Interpretation von Versuchsergebnissen mit dem Erweiterten Kernschmelzcode SCDAP/MODI
8. Dienst · Nucl. Technol. · 1984 · 65 · 10910.13182/NT84-A33378 ↗
9. Results of Experiment CORA W2
10. 1995
11. Veshchunov · J. Nucl. Mater. · 1996 · 231 · 110.1016/0022-3115(96)00367-4 ↗
12. Olander · J. Nucl. Mater. · 1997 · 247 · 25810.1016/S0022-3115(97)00052-4 ↗
13. Fink · J. Nucl. Mater. · 1995 · 226 · 4410.1016/0022-3115(95)00110-7 ↗
14. Abriata · Bull. Alloy Phase Diagrams · 1986 · 7 · 11610.1007/BF02881546 ↗
15. Olander · J. Electrochem. Soc. · 1984 · 131 · 216110.1149/1.2116041 ↗
16. On the flowing down the fuel rod of ZrUO liquefied mixture during severe accident at nuclear power plant