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Materials
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Nuclear Waste Forms: State-of-the-Art and Perspectives
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Nuclear Waste Forms: State-of-the-Art and Perspectives

A special issue of Materials (ISSN 1996-1944).

Deadline for manuscript submissions: closed (20 August 2022) | Viewed by 5167

Special Issue Editors

Dr. Philip Kegler

E-Mail Website
Guest Editor
Institute of Energy and Climate Research (IEK-6): Nuclear Waste Management and Reactor Safety, Forschungszentrum Jülich GmbH, 52425 Jülich, Germany
Interests: UO2 model systems; uranium chemistry; SIMFUEL; chromium doping; simulated spent fuel dissolution; uranium reference particles; microparticles
Dr. Stefan Neumeier

E-Mail Website
Guest Editor
Institute of Energy and Climate Research (IEK-6): Nuclear Waste Management and Reactor Safety, Forschungszentrum Jülich GmbH, 52425 Jülich, Germany
Interests: nuclear waste management; nuclear safeguards and forensics; uranium chemistry; spent nuclear fuel; ceramic waste forms; nuclear reference materials

Special Issue Information

Dear Colleagues,

The safe disposal of nuclear wastes is one of the major scientific and societal challenges of the coming decades. In this context, the knowledge of the behavior of different forms of nuclear waste is crucial for safety assessments of future deep geological repositories.

The Special Issue on “Nuclear Waste Forms: State of the Art and Perspectives” will give an overview on the design, performance, and properties of various nuclear waste forms for high-level radioactive waste (HLW). It will therefore provide in-depth information on a wide range of different radioactive waste forms, from spent nuclear fuel itself and simulated nuclear fuels, crystalline (ceramics), and non-crystalline waste forms (e.g., borosilicate glass) to specific waste forms that have been developed for the incorporation of special wastes.

This Special Issue welcomes contributions from all researchers working on all forms of nuclear waste forms, as well as on their characterization, properties, and applications. Experimental and theoretical considerations as well as modeling work are desired.

The Special Issue will cover but not be limited to the following topics:

  • Spent nuclear fuel;
  • All forms of simulated (spent) nuclear fuels (UO2 based model systems, SIMFUEL);
  • Ceramic waste forms, Synroc;
  • Vitrified nuclear waste;
  • Waste forms for specific waste streams.

It is our pleasure to invite you to submit a manuscript for this Special Issue. Full papers, communications, and reviews are welcome.

Dr. Philip Kegler
Dr. Stefan Neumeier
Guest Editors

Manuscript Submission Information

Manuscripts should be submitted online at www.mdpi.com by registering and logging in to this website. Once you are registered, click here to go to the submission form. Manuscripts can be submitted until the deadline. All submissions that pass pre-check are peer-reviewed. Accepted papers will be published continuously in the journal (as soon as accepted) and will be listed together on the special issue website. Research articles, review articles as well as short communications are invited. For planned papers, a title and short abstract (about 100 words) can be sent to the Editorial Office for announcement on this website.

Submitted manuscripts should not have been published previously, nor be under consideration for publication elsewhere (except conference proceedings papers). All manuscripts are thoroughly refereed through a single-blind peer-review process. A guide for authors and other relevant information for submission of manuscripts is available on the Instructions for Authors page. Materials is an international peer-reviewed open access semimonthly journal published by MDPI.

Please visit the Instructions for Authors page before submitting a manuscript. The Article Processing Charge (APC) for publication in this open access journal is 2600 CHF (Swiss Francs). Submitted papers should be well formatted and use good English. Authors may use MDPI's English editing service prior to publication or during author revisions.

Keywords

  • spent nuclear fuel
  • simulated nuclear fuel
  • ceramic waste forms
  • vitrified nuclear waste
  • nuclear waste forms
  • UO2
  • high level radioactive waste
  • actinides
  • specific waste forms

Published Papers (2 papers)

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Research

23 pages, 6436 KiB  
Article
Monazite-Type SmPO4 as Potential Nuclear Waste Form: Insights into Radiation Effects from Ion-Beam Irradiation and Atomistic Simulations
by Julia M. Leys, Yaqi Ji, Martina Klinkenberg, Piotr M. Kowalski, Hartmut Schlenz, Stefan Neumeier, Dirk Bosbach and Guido Deissmann
Materials 2022, 15(10), 3434; https://doi.org/10.3390/ma15103434 - 10 May 2022
Cited by 5 | Viewed by 1552
Abstract
Single-phase monazite-type ceramics are considered as potential host matrices for the conditioning of separated plutonium and minor actinides. Sm-orthophosphates were synthesised and their behaviour under irradiation was investigated with respect to their long-term performance in the repository environment. Sintered SmPO4 pellets and [...] Read more.
Single-phase monazite-type ceramics are considered as potential host matrices for the conditioning of separated plutonium and minor actinides. Sm-orthophosphates were synthesised and their behaviour under irradiation was investigated with respect to their long-term performance in the repository environment. Sintered SmPO4 pellets and thin lamellae were irradiated with 1, 3.5, and 7 MeV Au ions, up to fluences of 5.1 × 1014 ions cm−2 to simulate ballistic effects of recoiling nuclei resulting from α-decay of incorporated actinides. Threshold displacement energies for monazite-type SmPO4 subsequently used in SRIM/TRIM simulations were derived from atomistic simulations. Raman spectra obtained from irradiated lamellae revealed vast amorphisation at the highest fluence used, although local annealing effects were observed. The broadened, but still discernible, band of the symmetrical stretching vibration in SmPO4 and the negligible increase in P–O bond lengths suggest that amorphisation of monazite is mainly due to a breaking of Ln–O bonds. PO4 groups show structural disorder in the local environment but seem to behave as tight units. Annealing effects observed during the irradiation experiment and the distinctively lower dose rates incurred in actinide bearing waste forms and potential α-radiation-induced annealing effects indicate that SmPO4-based waste forms have a high potential for withstanding amorphisation. Full article
(This article belongs to the Special Issue Nuclear Waste Forms: State-of-the-Art and Perspectives)
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19 pages, 3786 KiB  
Article
Chromium Doped UO2-Based Ceramics: Synthesis and Characterization of Model Materials for Modern Nuclear Fuels
by Philip Kegler, Martina Klinkenberg, Andrey Bukaemskiy, Gabriel L. Murphy, Guido Deissmann, Felix Brandt and Dirk Bosbach
Materials 2021, 14(20), 6160; https://doi.org/10.3390/ma14206160 - 17 Oct 2021
Cited by 15 | Viewed by 2975
Abstract
Cr-doped UO2 as a modern nuclear fuel type has been demonstrated to increase the in-reactor fuel performance compared to conventional nuclear fuels. Little is known about the long-term stability of spent Cr-doped UO2 nuclear fuels in a deep geological disposal facility. [...] Read more.
Cr-doped UO2 as a modern nuclear fuel type has been demonstrated to increase the in-reactor fuel performance compared to conventional nuclear fuels. Little is known about the long-term stability of spent Cr-doped UO2 nuclear fuels in a deep geological disposal facility. The investigation of suitable model materials in a step wise bottom-up approach can provide insights into the corrosion behavior of spent Cr-doped nuclear fuels. Here, we present new wet chemical approaches providing the basis for such model systems, namely co-precipitation and wet coating. Both were successfully tested and optimized, based on detailed analyses of all synthesis steps and parameters: Cr-doping method, thermal treatment, reduction of U3O8 to UO2, green body production, and pellet sintering. Both methods enable the production of suitable model systems with a similar microstructure and density as a reference sample from AREVA. In comparison with results from the classical powder route, similar trends upon grain size and lattice parameter were determined. The results of this investigation highlight the significance of subtly different synthesis routes on the properties of Cr-doped UO2 ceramics. They enable a reproducible tailor-made well-defined microstructure, a homogeneous doping, for example, with lanthanides or alpha sources, the introduction of metallic particles, and a dust-free preparation. Full article
(This article belongs to the Special Issue Nuclear Waste Forms: State-of-the-Art and Perspectives)
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