Thermophysical characterization of nitrides inert matrices: Preliminary results on zirconium nitride

Ciriello, Antonio; Rondinella, V.V.; Staicu, D.; Somers, J.

doi:10.1016/j.jnucmat.2007.05.024

Cited by 17 publications

(17 citation statements)

References 12 publications

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“…This paper presents a comprehensive experimental study on ZrN and (Zr 1−x Pu x )N. The preliminary data and correlations reported in previous work on these materials [17,20,21] are here refined and presented encompassing extended temperature ranges and with a deeper analysis of the results. Low-temperature heat capacity data by semi-adiabatic calorimetry and high-temperature results by differential scanning calorimetry (DSC) are presented for the two compounds.…”

Section: Introductionmentioning

confidence: 92%

“…The ZrN powders were compressed and sintered into cylindrical pellets, which had a density (measured using Archimedes's immersion method in water) of 82.3% of the theoretical value (TD). The corresponding geometrical density was 80.5% [17].…”

Section: Zrnmentioning

confidence: 98%

“…In order to avoid high-temperature oxidation during the measurements, the samples were coated with graphite [17]. Among the materials characterized in this work, inactive ZrN samples could be coated using a sputter-coater device, (BAL-TEC SCD 500), while Pu-containing samples had to be coated manually by spraying a graphite layer onto the samples.…”

Section: Measurement Techniquesmentioning

confidence: 99%

“…[42] made also a theoretical calculation for the specific heat of ZrN, which was used in recent work by Basini et al [13] that provided new experimental data concerning heat capacity of both zirconium nitride and zirconium-plutonium nitride. Previous work by some of the present authors focused on thermophysical characterization of ZrN [17]. Hedge et al [43] published hightemperature thermal conductivity data for ZrN and Basini et al [13] reported conductivity data for the inert matrix containing plutonium.…”

Section: Introductionmentioning

confidence: 98%

See 3 more Smart Citations

Thermophysical characterization of ZrN and (Zr,Pu)N

Ciriello

Rondinella

Staicu

et al. 2009

Journal of Alloys and Compounds

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Section: Introductionmentioning

confidence: 92%

Section: Zrnmentioning

confidence: 98%

Section: Measurement Techniquesmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 98%

See 2 more Smart Citations

Thermophysical characterization of ZrN and (Zr,Pu)N

Ciriello

Rondinella

Staicu

et al. 2009

Journal of Alloys and Compounds

Self Cite

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“…Among them, the special attention is paid to nitrides of transition metals. They represent the greatest interest for the use as protective radiation-resistant materials in the nuclear-power installations of generation III+ and IV [3,4]. Interest in nitrides of transition metals is due to their special physical and mechanical properties, combining both properties of ceramics and metals.…”

Section: Introductionmentioning

confidence: 99%

Effects of Irradiation with Low-Energy and High-Energy Krypton Ions on the Structure of TiCrN Coatings

2015

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The results of surface structure investigations of TiCrN coating on carbon steel after irradiation by highand low energy krypton ions and successive two-hour vacuum annealing are reported in the present publication. Specimens with the TiCrN coatings of the 50 ÷ 100 nm thickness were formed by vacuum arc deposition techniques. The prepared specimens were irradiated by low energy (280 keV) and high energy (125 MeV) krypton ions. Study of surface structure was done by scanning electron microscopy and atomic force microscopy. X-ray diffraction and the Rutherford backscattering spectrometry were applied for determination of structure and coating thickness. After irradiation by high energy Kr ions there appear convexities of spherical shape with dimensions 10 ÷ 30 nm on the surface of the coating. Subsequent two-hour vacuum annealing led to decrease of convexities dimensions. Irradiation by low-energy Kr ions does not lead to significant changes in the structure of the coating surface. Only traces of surface sputtering are found. Explanation of the observed surface damage is proposed. Convexities are the traces of ions passing through coating and appear due to structural reconstruction at energy release along a trajectory of ions braking. As the projective range of high energy Kr ions exceeds coating thickness, then damage of structures is generated in the substrate and convexities are the traces of undersurface damages.

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Effect of the salt melt composition, temperature, and interaction time on the contact exchange reaction in the MCl-PbCl2-MeN systems

2008

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The interaction of titanium, zirconium, and aluminum nitrides with a mixture of fused alkali-metal chlorides with lead chloride at 870-1070 K is studied. It is shown that as a result of the contact exchange interaction, which occurs in no more than 5 h, a large fraction of the powdered nitrides transforms into a soluble state, and lead precipitates in a metallic form. The same behavior is also characteristic for compact hot-pressed samples of nitrides. The method proposed for transferring insoluble nitrides into a state which is soluble in salt systems can be used to recover mixed uranium-plutonium mononitride fuel and to fractionate fission products into high-, medium-, and low-level radioactive wastes.Safe and technologically adaptable methods for pyroelectrochemical recovery of spent nuclear fuel and fractionation of fission products in salt melts, allowing for more rapid and complete separation of uranium and plutonium, including from nitrides, are now being developed. The electrochemical separation of uranium and plutonium is performed at liquid or solid cathodes in LiCl-KCl melt in the temperature interval 773-873 K. First, the spent fuel is either chlorinated in the same melt or (U, Pu)N pellets are dissolved at the anode in LiCl-KCl-UCl 3 -PuCl 3 melt, after which uranium and plutonium settle on the solid cathode.The objective of the present work was to study the possibility of transferring aluminum, titanium, and zirconium nitrides into an ionic form by means of a contact exchange reaction with lead chloride in the temperature range 873-1073 K. This method can subsequently be used as an intermediate operation in the pyroelectrochemical recovery of spent mixed uranium-plutonium mononitride fuel. Uranium and plutonium nitrides are promising nuclear fuels, which are more effective, according to many parameters, than other types of fuel, for the new-generation fast reactors.Properties of Nitrides. Nitrides can be divided by the type of chemical bond into ionic, covalent, and metallic. The nitrides of metals from the first and second periods of the periodic table are ionic; their ions have outer s electrons. These nitrides are subject to hydrolysis with ammonia being released; they possess high electric resistance and are semiconductors. Boron, silicon, aluminum, gallium, and indium nitrides are covalent nitrides. Covalent nitrides are dielectrics with a wide band gap. Transition metals form nitrides with a metallic bond. These compounds are characterized by wide regions of homogeneity, high electric conductivity, positive temperature coefficient of the electric conductivity, high melting temperature, high hardness, and high formation enthalpy.Titanium, zirconium, uranium, and plutonium nitrides possess the same crystal lattices (plutonium nitride being an exception), close melting temperature, and close formation enthalpy, and they all exhibit metallic conductivity [1] (Table 1). It can be conjectured that certain other properties and behavior of these compounds will be similar and close [2,3]. For

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Thermophysical characterization of nitrides inert matrices: Preliminary results on zirconium nitride

Cited by 17 publications

References 12 publications

Thermophysical characterization of ZrN and (Zr,Pu)N

Thermophysical characterization of ZrN and (Zr,Pu)N

Effects of Irradiation with Low-Energy and High-Energy Krypton Ions on the Structure of TiCrN Coatings

Effect of the salt melt composition, temperature, and interaction time on the contact exchange reaction in the MCl-PbCl2-MeN systems

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