Influence de l'oxydation et de l'état structural sur les propriétés thermo-physiques d'un alliage à base de zirconium

Archambault, P.; Abrudeanu, Mărioara; Colleret, B.

doi:10.1016/0022-3115(93)90326-t

Cited by 4 publications

(6 citation statements)

References 3 publications

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“…The influence of structural transformations induced by thermal shocks of 60s, whose duration was determined by diffusivity measurements made at CANDU reactor operating temperatures (350°C), is shown in figure 6. Thermal shock temperature increase leads to diffusivity decrease, a phenomenon associated with grain size increase and with oxide layer degradation processes [16,29].…”

Section: Resultsmentioning

confidence: 99%

“…The diffusivity determinations for the specimens treated with a single thermal shock showed that thermal diffusivity decreases continuously as the shock temperature increases, a phenomenon which can be correlated with the increase of the metal mass grain size [16,29]. According to the existing literature, this phenomenon can be correlated with conductivity decrease through the increase of the oxide layer porosity [30].…”

Section: Discussionmentioning

confidence: 99%

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The Influence of Thermal Shocks on the Thermophisics Properties of the Zircaloy-4

Anghel¹,

Rosu²,

Neacsu³

et al. 2019

Rev. Chim.

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This paper presents the researches on the influence of thermal shocks on the heat transfer properties of the zircaloy-4, now used in fuel element cladding of third generation nuclear reactors. Thermal shock testing was performed using solar energy at high temperatures, up to 1350�C, with 1, 3 and 6 thermal cycles of 60s. The determination of the thermal diffusivity of the tested samples was made by the flash method at 350 �C, the operating temperature of the third-generation nuclear reactors.

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Section: Resultsmentioning

confidence: 99%

Section: Discussionmentioning

confidence: 99%

The Influence of Thermal Shocks on the Thermophisics Properties of the Zircaloy-4

Anghel¹,

Rosu²,

Neacsu³

et al. 2019

Rev. Chim.

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“…Fracture mechanics parameter, K IC , could be obtained by means of the Pin-Loading Test, and this method requires the existence of tube sample with a very sharp artificial mechanical defect [6]. In the case of PLT method, the tension is applied at one end of the sample in comparison with an axial tensile test on the same sample type [7][8][9]. The advantage is that the tension required for the deformation of the sample and the elastic deformation of the gripping system are lower than the uniaxial tensile test.…”

Section: Experimental Partmentioning

confidence: 99%

“…Polynomial fitting of compliance forFe-9Cr ODS Thus, the geometric function is given by the relation: (9) Here: t=0.6 mm; E=200 GPa -Young modulus [16]. By putting equation (8) into equation (9) the final form of the geometric function for Fe-9Cr ODS specimen is: (10) The fracture toughness K IC from PLT The fracture toughness could be obtained with equation (11): (11) and here the values of the factors a, t and w are known. Moreover, the P Q load values are obtained by analyzing experimental curves for the PLT tests as recommended by ASTM ( fig.7) [17][18][19].…”

Section: Obtaining Geometric Functionmentioning

confidence: 99%

Investigation of the Fracture Mechanics Properties of Small Tubes from Oxide Dispersion Strengthened Steels

Nitu¹,

Abrudeanu²,

Radu³

2019

Rev. Chim.

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The paper presents one part from the RATEN ICN contribution to the European FP7 MatISSE Project objectives, which is focused on the fracture mechanics properties of small tubes made from ODS steels (Oxide Dispersion Strengthened steels). The ODS tubes are foreseen as cladding tubes for gen IV reactors, and therefore the mechanical properties are very important for working in the most aggressive environment (irradiation and high temperatures) during the gen IV reactor operation. The fracture toughness, KIC, could be obtained for tubes with small diameters by means of the PLT-type mechanical test (acronym for Pin-Loading Test). This kind of test is a non-standard (ASTM) mechanical test, and during last decade it is still worldwide under development. The specific specimens for PLT-tests has been prepared from ODS tubes, which were provided to the project by the CEA France, a partner in the FP 7 MatISSE, in two different compositions: Fe -9cr ODS and Fe -14 Cr ODS. The paper highlights the PLT experimental test methodology, starting with obtaining of the geometric function, description of the experimental set-up and results processing.

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“…In a normal temperature regime, 350 °C, it forms on the surface a thin, compact and adherent oxide layer, with a protective character [ 13 , 14 , 15 , 16 ]. The accidental increase of the temperature towards high values determines the increase of the thickness and the modification of the structure of the corrosion layers, as well as important changes in the structure and properties of the alloy [ 17 , 18 , 19 , 20 , 21 , 22 ].…”

Section: Introductionmentioning

confidence: 99%

Structure and Heat Transfer in Zircaloy-4 Treated at High Temperatures

2021

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Zircaloy-4 has an important role in the construction of generation III nuclear reactors. An important application is the fuel element sheath, which must have excellent corrosion resistance in the working environment, adequate mechanical characteristics and very good heat transfer properties from the combustible element to the coolant. The corrosion processes at high temperatures, the accidents that lead to significant increases in temperature and the structural transformations associated with them affect the heat transfer process. The paper presents research on the influence of high temperatures on the microstructure and thermal diffusivity of the zy-4 alloy. The samples were treated in air, at temperatures between 850 and 1050 °C for 60 min. The corrosion layers were characterized microstructurally and chemically. Furthermore, the transformations produced in the base material under the corrosion layer were analyzed. The values of thermal diffusivity were determined and correlated with the structural transformations. Considering the state of research on the materials appropriate to be used for new generation reactors, the current importance of third-generation reactors for energy systems and the fact that they will operate in the coming years, we consider that the study offers useful outcomes in the field of nuclear energy.

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Influence de l'oxydation et de l'état structural sur les propriétés thermo-physiques d'un alliage à base de zirconium

Cited by 4 publications

References 3 publications

The Influence of Thermal Shocks on the Thermophisics Properties of the Zircaloy-4

The Influence of Thermal Shocks on the Thermophisics Properties of the Zircaloy-4

Investigation of the Fracture Mechanics Properties of Small Tubes from Oxide Dispersion Strengthened Steels

Structure and Heat Transfer in Zircaloy-4 Treated at High Temperatures

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