Neutron irradiation damage in aluminum oxide and nitride ceramics up to a fluence of 4.2×10

Yano, Toyohiko; Ichikawa, Kohki; Akiyoshi, Masafumi; Tachi, Yoshiaki

doi:10.1016/s0022-3115(00)00092-1

Cited by 74 publications

(35 citation statements)

References 22 publications

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“…The damage in a material caused by radiation can be classed by the type of energy transfer and the resultant implantation volume effects [108,109,97,100,110,99,111,112,113,114,115,116,117]. Gamma radiation, which is not covered here, produces little damage in the materials of interest.…”

Section: Radiation Damagementioning

confidence: 99%

Radiation Damage and Fission Product Release in Zirconium Nitride

Egeland

2005

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Zirconium nitride is a material of interest to the AFCI program due to some of its particular properties, such as its high melting point, strength and thermal conductivity. It is to be used as an inert matrix or diluent with a nuclear fuel based on transuranics. As such, it must sustain not only high temperatures, but also continuous irradiation from fission and decay products. This study addresses the issues of irradiation damage and fission product retention in zirconium nitride through an assessment of defects that are produced, how they react, and how predictions can be made as to the overall lifespan of the complete nuclear fuel package.Ion irradiation experiments are a standard method for producing radiation damage to a surface for observation. Cryogenic irradiations are performed to produce the maximum accumulation of defects, while elevated temperature irradiations may be used to allow defects to migrate and react to form clusters and loops. Cross-sectional transmission electron microscopy and grazing-incidence x-ray diffractometry were used in evaluating the effects that irradiation has on the crystal structure and microstructure of the material. Other techniques were employed to evaluate physical effects, such as nanoindentation and helium release measurements.Results of the irradiations showed that, at cryogenic temperatures, ZrN withstood over 200 displacements per atom without amorphization. No significant change to the lattice or microstructure was observed. At elevated temperatures, the large amount of damage showed mobility, but did not anneal significantly. Defect clustering was possibly observed, yet the size was too small to evaluate, and bubble formation was not observed.Defects, specifically nitrogen vacancies, affect the mechanical behavior of ZrN dramatically. Current and previous work on dislocations shows a distinct change in slip plane, which is evidence of the bonding characteristics. The stacking-fault energy changes dramatically with lowered nitrogen stoichiometry, resulting in widely spaced partial dislocations in ZrN with high nitrogen vacancy concentration.The wide range of nitrogen stoichiometry in the phase field shows that ZrN may accept nitrogen defects readily. Explanations for this are suggested based upon the bonding structure of these cubic nitrides. This structure allows for a solid framework to remain on one sublattice, while at the same time allowing defects on the other sublattice. This allowance for defects allows significant damage from irradiation yet also decreases the drive for cluster growth. This is evidence that the structure will be acceptable for long-term use as a nuclear reactor fuel.

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Section: Radiation Damagementioning

confidence: 99%

Radiation Damage and Fission Product Release in Zirconium Nitride

Egeland

2005

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“…As a result of microcrack formation, drastic decrease in bending strength of AlN happened. 19) Before occurrence of microcracking, lattice expansion is anisotropic manner in the specimen irradiated at relatively high temperatures, and isotropic in the specimen irradiated at lower temperatures. 20) In the specimen irradiated to 1.81 0 23 n/m 2 ( E n 0.1 MeV) at 100 C, changes in a and caxis lattice parameters and macroscopic length due to the irradi ation are the same values, i.e., isotropic, and also recovery behaviors of these values by annealing are the same man ner.…”

Section: Aluminum Nitridementioning

confidence: 99%

Structures of Dislocation Loops in Some Ceramics Induced by Fast Neutron Irradiation.

Yano

2003

J. Ceram. Soc. Japan

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¬«qAEËjCNcJm·åÛ¿ªµj±üT]ÊçôÓm\¢ îìLF HAEåw´qFHw¤C1528550 sÚaeåªR 2121Fast neutron emitted from the ssion or fusion nuclear reactions induces various kinds of crystalline defects into ceramics. These defects can cause degradation of material properties. Dislocation loops are frequently formed in crystalline materials after high uence fast neutron irradiation. These structures have been ana lyzed based on highresolution electron microscopy and image simulations based on defects models. Local atomic congurations of interstitial loops formed in SiC, AlN and Si 3 N 4 are reviewed. These loops are com monly formed on the closest packing plane in each crystal, and more than one layer is arranged to form specic atomic congurations in spite of an extra thickness corresponding only one tetrahedral layer. Physi cal property changes of these materials are discussed based on the presence of these defects.

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“…The main drawback for the use of aluminum nitride in nuclear facilities is its ability to generate a radioactive long-lived isotope 14 C by transmutation of 14 N [6]. Nevertheless, this drawback can be reduced by the use of isotope tailored material, in which 15 N replaces 14 N [7].…”

Section: Introductionmentioning

confidence: 99%

“…Nevertheless, this drawback can be reduced by the use of isotope tailored material, in which 15 N replaces 14 N [7].…”

Section: Introductionmentioning

confidence: 99%

Effect of swift heavy ion irradiations in polycrystalline aluminum nitride

Nappé

Benabdesselam

Grosseau

et al. 2011

Nuclear Instruments and Methods in Physics Research Section B:

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Thanks to its high thermal conductivity, aluminum nitride may be a serious candidate as fuel coating for the Gas Fast Reactor. However, its behavior under irradiation is not entirely well understood. In order to catch a glimpse of this behavior, specimens were irradiated with swift heavy ions of different energies then characterised by both thermally stimulated luminescence and optical absorption spectrophotometry. With these techniques, the native defects, as well as those affected by irradiation, were identified: thus, by comparison to the virgin sample, no new defect detectable by these techniques is created by irradiations. Eventually, the fact that these techniques complement each other allowed to understand the effect of irradiation parameters on the defect concentration.

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Neutron irradiation damage in aluminum oxide and nitride ceramics up to a fluence of 4.2×10

Cited by 74 publications

References 22 publications

Radiation Damage and Fission Product Release in Zirconium Nitride

Radiation Damage and Fission Product Release in Zirconium Nitride

Structures of Dislocation Loops in Some Ceramics Induced by Fast Neutron Irradiation.

Effect of swift heavy ion irradiations in polycrystalline aluminum nitride

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