On the effects of fission product noble metal inclusions on the kinetics of radiation induced dissolution of spent nuclear fuel

Trummer, Martin; Nilsson, Sara; Jönsson, Mats

doi:10.1016/j.jnucmat.2008.04.018

Cited by 56 publications

(47 citation statements)

References 21 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…On the basis of this observation a reaction where the noble metal inclusions catalyze the reduction of U(VI) to U(IV) by H 2 on the surface of the pellet was postulated [71]. This reaction was later verified using Pd particle-doped UO 2 pellets exposed to H 2 O 2 and H 2 [59]. In these experiments, Pd-doped pellets with different Pd concentrations were exposed to aqueous solutions containing H 2 O 2 and HCO 3 − at different partial pressures of H 2 .…”

Section: Influence Of Groundwater Componentsmentioning

confidence: 90%

“…UO 2 doped with α-emitting nuclides [51][52][53][54][55][56][57][58] has been used to mimic the radiation field from spent nuclear fuel older than 1000 years. UO 2 has been doped with Pd particles [59,60] to mimic the effect of ε-phase particles (fission products forming noble metal inclusions in the fuel matrix) and with rare earth oxides [61][62][63] to mimic the effect of fission products forming oxides in the fuel matrix. SIMFUEL is a more complex material produced to mimic some of the chemical properties of spent nuclear fuel.…”

Section: Kinetics Of Surface Reactionsmentioning

confidence: 99%

See 1 more Smart Citation

Radiation Effects on Materials Used in Geological Repositories for Spent Nuclear Fuel

Jönsson

2012

ISRN Materials Science

Self Cite

View full text Add to dashboard Cite

Safe long-term storage of radioactive waste from nuclear power plants is one of the main concerns for the nuclear industry as well as for governments in countries relying on electricity produced by nuclear power. A repository for spent nuclear fuel must be safe for extremely long time periods (at least 100 000 years). In order to ascertain the long-term safety of a repository, extensive safety analysis must be performed. One of the critical issues in a safety analysis is the long-term integrity of the barrier materials used in the repository. Ionizing radiation from the spent nuclear constitutes one of the many parameters that need to be accounted for. In this paper, the effects of ionizing radiation on the integrity of different materials used in a granitic deep geological repository for spent nuclear fuel designed according to the Swedish KBS-3 model are discussed. The discussion is primarily focused on radiationinduced processes at the interface between groundwater and solid materials. The materials that are discussed are the spent nuclear fuel (based on UO 2 ), the copper-covered iron canister, and bentonite clay. The latter two constitute the engineered barriers of the repository.

show abstract

Section: Influence Of Groundwater Componentsmentioning

confidence: 90%

Section: Kinetics Of Surface Reactionsmentioning

confidence: 99%

Radiation Effects on Materials Used in Geological Repositories for Spent Nuclear Fuel

Jönsson

2012

ISRN Materials Science

Self Cite

View full text Add to dashboard Cite

show abstract

“…The possible reasons for the enhanced dissolution of irradiated fuels are expected to be, for example, the catalytic effect of noble metal fission products such as Pd on the oxidizing dissolution of UO 2 , the evolution of the effective surface area of the fuels by irradiation, or a decrease in the solid density of the fuels upon irradiation. As for the catalytic effect of noble metals, Trummer et al [17] reported that UO 2 powders containing 3 wt% of Pd dissolved five to six times faster than non-Pd powders in H 2 O 2 þ HCO 3 solution. The same effect of noble metals was also reported by Ikeda et al [18].…”

Section: Promotion Effect By Irradiationmentioning

confidence: 99%

Dissolution behavior of irradiated mixed oxide fuel with short stroke shearing for fast reactor reprocessing

Ikeuchi

Sano

Shibata

et al. 2013

Journal of Nuclear Science and Technology

View full text Add to dashboard Cite

An efficient dissolution process was established for future reprocessing in which mixed-oxide (MOX) fuels with high plutonium contents and dissolver solution with high heavy-metal (HM) concentrations (more than 500 g dm 73 ) will be treated. This dissolution process involves short stroke shearing of fuels (*10 mm in length). The dissolution kinetics of irradiated MOX fuels and the effects of the Pu content, HM concentration, and fuel form on the dissolution rate were investigated. Irradiated fuel was found to dissolve as 10 2 -10 3 times fast as non-irradiated fuel, but the rate decreased with increasing Pu content. Kinetic analysis based on the fragmentation model, which considers the penetration and diffusion of nitric acid through fuel matrices prior to chemical reaction, indicated that the dissolution rate of irradiated fuel was affected not only by the volume ratio of liquid to solid (L/S ratio) but also by the exposed surface area per unit mole of nitric acid (A/m ratio). The penetration rate of nitric acid is expected to be decreased at high HM concentrations by a reduction in the L/S ratio, but enhanced by shearing the fuel pieces with short strokes and thus enlarging the A/m ratio.

show abstract

“…Leaching experiments with SNF and UO 2 (s) samples as well as electrochemical studies in diluted Na + -Cl − -HCO 3 − / CO 3 2− solutions demonstrate clearly a hydrogen inhibition effect mediated by Ru-Pd-Rh-doping and ε-particles [133][134][135][136][137][138][139]]. An ε-particle surface mediated hydrogen effect depends on the availability of these particles and might be affected by "poisoning" of these noble metal alloys with dissolved sulfides present in the near-field, whereas a radiolytic driven hydrogen effect will be weakened by counteracting groundwater constituents, such as bromide.…”

Section: Radionuclide Release Due To Corrosion Of the Uo 2 Matrixmentioning

confidence: 99%

Radionuclide behaviour in the near-field of a geological repository for spent nuclear fuel

et al. 2012

View full text Add to dashboard Cite

UO 2 fuel corrosion / Radionuclide release / Instant release fraction / Hydrogen effect / Coprecipitation / SorptionSummary. Even though chemical processes related to the corrosion of spent nuclear fuel in a deep geological repository are of complex nature, knowledge on underlying mechanisms has very much improved over the last years. As a major result of numerous studies it turns out that alteration of irradiated fuel is significantly inhibited under the strongly reducing conditions induced by container corrosion and consecutive H 2 production. In contrast to earlier results, radiolysis driven fuel corrosion and oxidative dissolution appears to be less relevant for most repository concepts. The protective hydrogen effect on corrosion of irradiated fuel has been evidenced in many experiments. Still, open questions remain related to the exact mechanism and the impact of potentially interfering naturally occurring groundwater trace components. Container corrosion products are known to offer considerable reactive surface area in addition to engineered buffer and backfill material. In combination, waste form, container corrosion products and backfill material represent strong barriers for radionuclide retention and retardation and thus attenuate radionuclide release from the repository near-field.

show abstract

On the effects of fission product noble metal inclusions on the kinetics of radiation induced dissolution of spent nuclear fuel

Cited by 56 publications

References 21 publications

Radiation Effects on Materials Used in Geological Repositories for Spent Nuclear Fuel

Radiation Effects on Materials Used in Geological Repositories for Spent Nuclear Fuel

Dissolution behavior of irradiated mixed oxide fuel with short stroke shearing for fast reactor reprocessing

Radionuclide behaviour in the near-field of a geological repository for spent nuclear fuel

Contact Info

Product

Resources

About