Transmutation of actinides in inert-matrix fuels: fabrication studies and modelling of fuel behaviour

Konings, R.J.M.; Bakker, K.; Boshoven, Jacobus; Hein, H.; Huntelaar, M.E.; Laan, R.R. van der

doi:10.1016/s0022-3115(99)00043-4

Cited by 49 publications

(21 citation statements)

References 12 publications

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“…2 IMF could also be a waste form for direct disposal after one cycle of burn-up and/or a transmutation target to decrease the radiotoxicity of minor actinides. 3 Candidate materials for these applications must satisfy a few mandatory criteria such as structural stability and efficient radionuclides confinement under irradiation (see, e.g., Ref. 4).…”

Section: Introductionmentioning

confidence: 99%

Comprehensive study of the effect of the irradiation temperature on the behavior of cubic zirconia

Debelle

Channagiri

Thomé

et al. 2014

Journal of Applied Physics

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High-temperature stability of ion-implanted zirconia and spinel J. Appl. Phys. 97, 113509 (2005) ) and at five temperatures: 80, 300, 573, 773, and 1073 K. Irradiated samples have been characterized by Rutherford backscattering spectroscopy in channeling mode, X-ray diffraction and transmission electron microscopy techniques in order to determine the disordering kinetics. All experimental results show that, whatever is the irradiation temperature, the damage build-up follows a multi-step process. In addition, the disorder level at high fluence is very similar for all temperatures. Thus, no enhanced dynamic annealing process is observed. On the other hand, transitions in the damage accumulation process occur earlier in fluence with increasing temperature. It is shown that temperature as low as 573 K is sufficient to accelerate the disordering process in ion-irradiated YSZ. V C 2014 AIP Publishing LLC. [http://dx

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Section: Introductionmentioning

confidence: 99%

Comprehensive study of the effect of the irradiation temperature on the behavior of cubic zirconia

Debelle

Channagiri

Thomé

et al. 2014

Journal of Applied Physics

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“…AFCI relies mostly on fast-moving neutrons for fission or to transmute the transuranics to less stable isotopes [18,13,21,22,23], although thermal neutrons can also be used. The less stable isotopes then decay rapidly to a more stable form through a decay cascade.…”

Section: Reactors For Afci Usementioning

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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“…Konings et al [16] discussed the 'ideal' characteristics of the dispersion-type fuel in terms of size, distribution and its 'host' matrix.…”

Section: Development Of Fabrication Tech-nologymentioning

confidence: 99%

Inert matrix fuel — A new challenge for material technology in the nuclear fuel cycle

et al. 2001

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An innovative nuclear fuel concept for the utilization as energy resources and for the incineration of excess Pu arisings as well as for an effective transmutation of minor actinides (MA's; Am, Np and Cm) is discussed from the aspect of material technology. Stabilized cubic phase ZrO 2 and other potential candidate materials for the Inert Matrix are compared in terms of the material properties and other behaviors such as the behavior against irradiation with the relevant information currently available. Strategies for the use of the Inert Matrix Fuel concept in various countries are discussed and compared for their options in nuclear fuel cycle technology.

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Transmutation of actinides in inert-matrix fuels: fabrication studies and modelling of fuel behaviour

Cited by 49 publications

References 12 publications

Comprehensive study of the effect of the irradiation temperature on the behavior of cubic zirconia

Comprehensive study of the effect of the irradiation temperature on the behavior of cubic zirconia

Radiation Damage and Fission Product Release in Zirconium Nitride

Inert matrix fuel — A new challenge for material technology in the nuclear fuel cycle

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