Spent Fuel as Waste Material

Carbol, Paul; Wegen, D.; Wiss, T.; Fors, Patrik

doi:10.1016/b978-0-08-056033-5.00106-3

Cited by 22 publications

(27 citation statements)

References 84 publications

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“…Examples for formation water compositions are presented in [11,31]. Due to the high residence times of the formation/pore water in the considered bedrocks, the natural solutions are close to saturation with respect to the primary rock-forming minerals or fracture filling materials [31].…”

Section: Groundwater Compositionsmentioning

confidence: 99%

“…Afterwards β-and γ -emitters of SNF will have significantly decayed, whereas high inventories of long-lived α-emitters will persist for a much longer time span (e.g. [11]). …”

Section: Radiolysis Of Aqueous Solutionmentioning

confidence: 99%

“…Different engineered barriers have been developed, comprising thick-walled containers for SNF, overpacks, buffer/backfill and plugging materials for the specific requirements defined by the respective geological formations. Detailed descriptions of international final disposal concepts have been presented in recent reviews [9][10][11][12]. In the next paragraphs the main characteristics of the various engineered barriers systems for SNF are briefly summarized.…”

Section: Overview On Relevant Properties In the Near-field Of A Geolomentioning

confidence: 99%

“…Detailed descriptions of the radionuclide distribution in spent nuclear fuel and the radiochemical properties are given for instance by Kleykamp [51], Carbol et al [11] and Neeb [49].…”

Section: Alteration Of Spent Nuclear Fuel and Radionuclide Release Unmentioning

confidence: 99%

“…The protective hydrogen effect is considered to be related to three different electrochemical, radiochemical and radiolytically driven processes [11,73]:…”

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

confidence: 99%

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

et al. 2012

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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.

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Section: Groundwater Compositionsmentioning

confidence: 99%

“…Afterwards β-and γ -emitters of SNF will have significantly decayed, whereas high inventories of long-lived α-emitters will persist for a much longer time span (e.g. [11]). …”

Section: Radiolysis Of Aqueous Solutionmentioning

confidence: 99%

Section: Overview On Relevant Properties In the Near-field Of A Geolomentioning

confidence: 99%

“…Detailed descriptions of the radionuclide distribution in spent nuclear fuel and the radiochemical properties are given for instance by Kleykamp [51], Carbol et al [11] and Neeb [49].…”

Section: Alteration Of Spent Nuclear Fuel and Radionuclide Release Unmentioning

confidence: 99%

“…The protective hydrogen effect is considered to be related to three different electrochemical, radiochemical and radiolytically driven processes [11,73]:…”

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

confidence: 99%

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

et al. 2012

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Research for the Safe Management of Nuclear Waste at Forschungszentrum Jülich: Materials Chemistry and Solid Solution Aspects

et al. 2020

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Ultra‐Selective and Efficient Static/Dynamic Palladium Capture from Highly Acidic Solution with Robust Macrocycle‐Based Polymers

Wang

et al. 2023

Adv Funct Materials

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The capture of palladium from spent nuclear fuel is crucial for the sustainable development of nuclear energy and resource recovery. One of the most challenging issues in this direction is the survival of adsorbents under extreme reprocessing conditions such as strongly acidic media and high radiation fields while still maintaining high extraction ability and selectivity. Herein, an approach to addressing this issue is reported by incorporating macrocycle into nitrogen‐rich covalent organic polymers (COPs). Dramatically outperforming current adsorbing materials, pillar[5]arene‐based COPs with pyridyl and triazolyl functionalities display record adsorption capacity for Pd(II) at 3 M HNO3 (403 mg g−1), extraordinary stability under 500 kGy gamma irradiation, and ultra‐high selectivity toward Pd(II) over both 17 coexisting cations and six anions. In particular, the material P5COP‐m‐BPT with the best performance also shows remarkable dynamic adsorption efficiency for Pd(II). This study not only provides a strategy to enhance all‐sided adsorption performance in palladium separation with nitrogen‐rich COPs materials but also demonstrates the superiority of customizing advanced materials with macrocycles.

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Spent Fuel as Waste Material

Cited by 22 publications

References 84 publications

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

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

Research for the Safe Management of Nuclear Waste at Forschungszentrum Jülich: Materials Chemistry and Solid Solution Aspects

Ultra‐Selective and Efficient Static/Dynamic Palladium Capture from Highly Acidic Solution with Robust Macrocycle‐Based Polymers

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