Properties and characteristics of corium prototype of a fast power reactor
Mukhamedov N. Kukushkin I. Vityuk V. Vityuk G. Dolzhikov S. Sapatayev Y.
May 2025Elsevier Ltd
Annals of Nuclear Energy
2025#214
This paper focuses on the study of properties and characteristics of corium of a fast power reactor resulted from physical simulation in the VCG-135 test-bench. The structure, phase composition and thermophysical properties (specific heat capacity, thermal diffusivity and thermal conductivity) were studied and compression tests were implemented. According to elemental analysis, corium consists predominantly of uranium. Based on the results of X-ray phase analysis, it was established that the main structural component of prototype corium specimens is UO2 with a face-centered cubic lattice and an evaluated lattice parameter a = 0.5472 ± 0.0002 nm; the second structural component was identified as an intermetallic U6Fe phase with a tetragonal lattice. Due to the presence of pores and cracks in the structure, the specimens fail stepwise and have low ultimate failure load.
Material carbonization , Melting crucible , Prototype corium of nuclear reactor , Stainless steel , Thermophysical properties , Uranium dioxide
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National Nuclear Center of the Republic of Kazakhstan, 2 Beibyt atom St., Kurchatov, 180010, Kazakhstan
National Nuclear Center of the Republic of Kazakhstan
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