Sébastien Caes , Andrey Bukaemskiy , Céline Cannes , Sylvie Delpech , Valdir De Souza , Bruno Kursten
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引用次数: 0
Abstract
Metallic beryllium is an attractive material for nuclear applications, e.g. thermal reactor and fusion reactors. After use, activated beryllium waste will need to be disposed of in a geological disposal repository. One option for the treatment and conditioning of the beryllium waste could be the direct emplacement of pieces of beryllium in a cementitious matrix. In these conditions, beryllium corrodes due to reaction with water to produce hydrogen, and beryllium hydroxide, leading to possible loss of the waste containment. To gain more information on the anaerobic corrosion of beryllium, Electrochemical Impedance Spectroscopy and hydrogen measurement by gas chromatography were used, while beryllium samples were immersed in solutions representative of promising matrices (Portland cement (OPC, pH 13.5) and magnesium phosphate cement (MPC, pH 8.1)) for maximum one year. At the beginning of the test (< 180 days), both techniques showed that the beryllium corrosion rate was lower in OPC solution than in MPC solution. At longer term (> 180 days), the corrosion rate decreased sharply in MPC solution, while the corrosion rate in OPC solution remained stable. Therefore, at longer term, the lower corrosion rate was observed in MPC solution. The reason of this corrosion rate decrease comes from the formation of a passive layer composed of Be(OH)2 (inner part) and KBePO4·H2O crystals (outer part) at the surface of beryllium in MPC solution, while no protective corrosion product layer was present on the metal surface in OPC solution. In that later case, pitting corrosion was observed in addition to the dissolution of beryllium species in solution probably in the form of Be(OH)42−.
期刊介绍:
The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome.
The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example.
Topics covered by JNM
Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior.
Materials aspects of the entire fuel cycle.
Materials aspects of the actinides and their compounds.
Performance of nuclear waste materials; materials aspects of the immobilization of wastes.
Fusion reactor materials, including first walls, blankets, insulators and magnets.
Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties.
Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.