Evolution of spent nuclear fuel in dry storage conditions for millennia and beyond

Wiss, T.; Hiernaut, J.-P.; Roudil, D.; Colle, Jean‐Yves; Maugeri, E. A.; Talip, Zeynep; Janssen, André; Rondinella, V.V.; Konings, R.J.M.; Matzke, Hansjoachim; Weber, William J.

doi:10.1016/j.jnucmat.2014.03.055

Cited by 63 publications

(45 citation statements)

References 56 publications

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“…2 of Ref. 22 , our value of radiation damage (0.15 dpa), coupled with a swelling of 0.6 %, does appear consistent with many current studies, and does suggest a reduction would be observed in the thermal conductivity. This agrees with the observations we have made in changes of the linewidths of the acoustic phonons.…”

Section: A Extent Of Radiation Damagesupporting

confidence: 91%

“…This would correspond to ∼ 5 × 10 17 alpha-decay events/g, and have a swelling of 0.7 % (Table 1 Ref. 22 ) compared with the swelling we produced of ∼ 0.6% (i.e. ∆a/a = 0.56 %).…”

Section: A Extent Of Radiation Damagementioning

confidence: 59%

“…In the storage case ( Fig. 1 of Ref 22 ) damage of ∼ 0.15 dpa corresponds approximately to the activity of moderately radiated 60 GWd/t (gigawatt days per ton) fuel when it is removed from the reactor. This would correspond to ∼ 5 × 10 17 alpha-decay events/g, and have a swelling of 0.7 % (Table 1 Ref.…”

Section: A Extent Of Radiation Damagementioning

confidence: 99%

“…The first relates to damage of the fuel, and the formation of the high burn-up structure in nuclear fuels 21 . The second is long-term storage of irradiated nuclear fuel, and what happens to the fuel as a function of time 22 . In the storage case ( Fig.…”

Section: A Extent Of Radiation Damagementioning

confidence: 99%

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Study of phonons in irradiated epitaxial thin films of UO2

et al. 2018

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We report experiments to determine the effect of radiation damage on the phonon spectra of the most common nuclear fuel, UO2. We have irradiated thin (∼ 300 nm) epitaxial films of UO2 with 2.1 MeV He 2+ ions to 0.15 dpa and a lattice swelling of ∆a/a ∼ 0.6 %, and then used grazingincidence inelastic X-ray scattering to measure the phonon spectrum. We succeeded to observe the acoustic modes, both transverse and longitudinal, across the Brillouin zone. The phonon energies, in both the pristine and irradiated samples, are unchanged from those observed in bulk material. On the other hand, the phonon linewidths (inversely proportional to the phonon lifetimes), show a significant broadening when comparing the pristine and irradiated samples. This effect is shown to increase with phonon energy across the Brillouin zone. The decreases in the phonon lifetimes of the acoustic modes are roughly consistent with a 50% reduction in the thermal conductivity.

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Section: A Extent Of Radiation Damagesupporting

confidence: 91%

“…This would correspond to ∼ 5 × 10 17 alpha-decay events/g, and have a swelling of 0.7 % (Table 1 Ref. 22 ) compared with the swelling we produced of ∼ 0.6% (i.e. ∆a/a = 0.56 %).…”

Section: A Extent Of Radiation Damagementioning

confidence: 59%

Section: A Extent Of Radiation Damagementioning

confidence: 99%

Section: A Extent Of Radiation Damagementioning

confidence: 99%

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Study of phonons in irradiated epitaxial thin films of UO2

et al. 2018

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“…The behavior of He in UO 2 has been extensively analyzed mainly in the frame of long-term disposal of spent nuclear fuel, where helium is produced by the alpha-decay of actinides produced during in-pile irradiation [1]- [3]. Such studies have included many aspects: He behavior (lattice location [4], diffusion and precipitation [5]- [7] [8]) but also created defect [9] and the induced strains in the UO 2 matrix [10].…”

Section: Introductionmentioning

confidence: 99%

Strain relaxation in He implanted UO2 polycrystals under thermal treatment: An in situ XRD study

Palancher

Kachnaoui

Martin

et al. 2016

Journal of Nuclear Materials

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Within the frame of the long-term evolution of spent nuclear fuel in dry disposal, the behavior of He in UO 2 polycrystals has to be studied. In this paper, strain relaxation in He implanted samples have been characterized using in-situ X-ray diffraction during thermal annealing. The influence of a wide range of experimental parameters (annealing atmosphere, He ion energy, orientation of the UO 2 grains probed by X-rays) has been evaluated. If each of them contributes to the strain relaxation kinetics in the implanted layer, strain relaxation is not completed for temperatures below 900 °C which is equivalent to what has been found on He implanted UO 2 single crystals, or aged UO 2 pellets doped with α-emitters. This stands for an additional evidence of the interest of ion implantation to simulate self-irradiation in spent nuclear fuel. Moreover, in the case of implantation with 500 keV He ions, we clearly show that strain relaxation and He release are not correlated for temperatures below 750 °C and demonstrate that this applied in-situ approach is well-suited for measuring strains in ion implanted polycrystals.

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Behaviour and Properties of Nuclear Fuels

Konings

Bertolus

2018

Experimental and Theoretical Approaches to Actinide Chemistry

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Evolution of spent nuclear fuel in dry storage conditions for millennia and beyond

Cited by 63 publications

References 56 publications

Study of phonons in irradiated epitaxial thin films of UO2

Study of phonons in irradiated epitaxial thin films of UO2

Strain relaxation in He implanted UO2 polycrystals under thermal treatment: An in situ XRD study

Behaviour and Properties of Nuclear Fuels

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