Inductive cold crucible melting of actinide-bearing murataite-based ceramics

Stefanovsky, S. V.; Ptashkin, A.G.; Knyazev, O. A.; Дмитриев, С. А.; Yudintsev, S. V.; Никонов, Б. С.

doi:10.1016/j.jallcom.2007.01.067

Cited by 27 publications

(15 citation statements)

References 9 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…These results suggest that the powellite phase materials exhibit stability to 1000 years at anticipated doses (2×10 10 -2×10 11 Gy) based on current commercial HLW glasses [1]. The structural change was observed on in situ electron irradiated CaMoO 4 and BaMoO 4 after 10 13 Gy which suggests both powellite materials have similar radiation stability upon β-particles and -emissions. It is noted that actual self-irradiation during waste form storage would come from β-particles fluxes which are orders of magnitude lower than that used in TEM irradiation experiments.…”

Section: Methodsmentioning

confidence: 63%

“…However, recent work has shown that they can also be produced from a melt process analogous to GCM processing. For example, demonstrations have been completed using the Cold Crucible Induction Melter (CCIM) technology to produce several crystalline ceramic waste forms, including murataite-rich ceramics, [13,14] zirconolite/pyrochlore ceramics, [15] Synroc-C (zirconolite, hollandite, perovskite), [16,17] aluminotitanate ceramics, and zirconia [18]. This production route is advantageous since melters are already in use for commercial and defense high level waste (HLW) vitrification in several countries, and melter technology greatly reduces the potential for airborne contamination as compared to processes involving extensive powder handling operations.…”

mentioning

confidence: 99%

See 1 more Smart Citation

Single phase melt processed powellite (Ba,Ca)MoO4 for the immobilization of Mo-rich nuclear waste

Brinkman

Fox

Marra

et al. 2013

Journal of Alloys and Compounds

View full text Add to dashboard Cite

Crystalline and glass composite materials are currently being investigated for the immobilization of combined High Level Waste (HLW) streams resulting from potential commercial fuel reprocessing scenarios. Several of these potential waste streams contain elevated levels of transition metal elements such as molybdenum (Mo). Molybdenum has limited solubility in typical silicate glasses used for nuclear waste immobilization.Under certain chemical and controlled cooling conditions, a powellite (Ba,Ca)MoO 4 crystalline structure can be formed by reaction with alkaline earth elements. In this study, single phase BaMoO 4 and CaMoO 4 were formed from carbonate and oxide precursors demonstrating the viability of Mo incorporation into glass, crystalline or glass composite materials by a melt and crystallization process. X-ray diffraction, photoluminescence, and Raman spectroscopy indicated a long range ordered crystalline structure. In-situ electron irradiation studies indicated that both CaMoO 4 and BaMoO 4 powellite phases exhibit radiation stability up to 1000 years at anticipated doses with a crystalline to *Manuscript Click here to view linked References amorphous transition observed after 1 X 10 13 Gy. Aqueous durability determined from product consistency tests (PCT) showed low normalized release rates for Ba, Ca, and Mo (<0.05 g/m 2 ).

show abstract

Section: Methodsmentioning

confidence: 63%

mentioning

confidence: 99%

Single phase melt processed powellite (Ba,Ca)MoO4 for the immobilization of Mo-rich nuclear waste

Brinkman

Fox

Marra

et al. 2013

Journal of Alloys and Compounds

View full text Add to dashboard Cite

show abstract

“…Several groups have published throughputs of their CCIM on a mass per time per area basis, for example [18,[30][31][32]. Stefanovsky, et al, give a process throughput rate of 890 kg/m 2 /hr [processed 2.7 kg in 20 min (8.1 kg/hr) in a 108 mm ID CCIM = 884.2 kg/m 2 /hr] [32].…”

Section: Throughput To Be Competitive With Hip Processingmentioning

confidence: 99%

Extended Development Work to Validate a HLW Calcine Waste Form via INL's Cold Crucible Induction Melter

King¹,

Maio²

2011

View full text Add to dashboard Cite

To accomplish high level waste (HLW) calcine treatment objectives, the Idaho Clean-up Project contractor at the Idaho National Laboratory (INL), CWI, has chosen to immobilize the calcine in a glassceramic via the use of a Hot-Isostatic-Press (HIP). The choice for HIPing has been formally documented in a 2010 Record of Decision (ROD). Even though the HIP process may prove suitable for the calcine as specified in the ROD and validated in a number of past value engineering sessions, DOE is evaluating back-up treatment methods for the calcine as a result of the technical, schedule, and cost risk associated with the HIPing process. Consequently DOE-HQ has requested DOE-ID to make INL's bench-scale coldcrucible induction melter (CCIM) available for investigating its viability as a process alternate to calcine treatment.Providing a solid, stable, low volume and durable material that can be easily stored and/or disposed is the rationale for the immobilization of radioactive waste material (i.e. HLW calcine) in either a glass, ceramic, or glass-ceramic form. In addition, the waste form is the most controllable of the key components in immobilizing and isolating radioactive waste in a deep geological repository. In general ceramic and glass-ceramics waste forms offer an alternative to the traditional borosilicate glass HLW forms. Ceramics typically accommodate higher waste loadings than borosilicate glass, leading to smaller intermediate and long-term disposal facilities. Many ceramic phases are known to possess superior chemical durability as compared to borosilicate glass due to their similarity to natural analog minerals that geologically contain natural actinides. However, pure ceramics are generally multiphase systems containing many minor phases that make characterization and prediction of performance challenging within a repository environment. Therefore, many investigators have proposed using glass-ceramics as a compromise between the more inexpensive, easier to characterize glass waste forms and the more durable ceramic waste forms. Glass-ceramics have several advantages over traditional borosilicate glasses as a waste form. Borosilicate glasses can inadvertently denitrify, leading to a less durable product that could crack during cooling and unwanted crystals may be prone to dissolution. By designing glass-ceramics, the risks of deleterious effects from devitrification are removed. Glass-ceramics should provide a waste form with the advantages of both glass and ceramics-ease of manufacture (especially via the CCIM)-with improved mechanical properties, thermal stability, and chemical durability.The INL's bench-scale CCIM is a unique technology that is extremely well suited for the generation of all these types of waste forms, especially glass-ceramics. The CCIM's attributes, if validated through testing, may provide a calcine waste form and a corresponding waste process that results in high waste form durability, loading, throughput, and robustness; all of which may be equivalent or superior to the HIPing...

show abstract

“…6 While these materials are typically densified via hot isostatic pressing, recent work has shown that they can also be produced from a melt. For example, demonstrations have been completed using the Cold Crucible Induction Melter (CCIM) technology to produce several crystalline ceramic waste forms, including murataite-rich ceramics, 7 zirconolite/pyrochlore ceramics, 8 Synroc-C (zirconolite, hollandite, perovskite), 9 aluminotitanate ceramics, and zirconia. 10 This production route is advantageous since melters are already in use for defense high level waste (HLW) vitrification in several countries, and melter technology greatly reduces the potential for airborne contamination as compared to powder handling operations.…”

Section: Introductionmentioning

confidence: 99%

Development of Crystalline Ceramics for Immobilization of Advanced Fuel Cycle Reprocessing Wastes

Fox¹,

Brinkman²

2011

View full text Add to dashboard Cite

SUMMARYThe Savannah River National Laboratory (SRNL) is developing crystalline ceramic waste forms to incorporate CS/LN/TM high Mo waste streams consisting of perovskite, hollandite, pyrochlore, zirconolite, and powellite phase assemblages. Simple raw materials, including Al 2 O 3 , CaO, and TiO 2 were combined with simulated waste components to produce multiphase crystalline ceramics. Fiscal Year 2011 (FY11) activities included i) expanding the compositional range by varying waste loading and fabrication of compositions rich in TiO 2 , ii) exploring the processing parameters of ceramics produced by the melt and crystallize process, iii) synthesis and characterization of select individual phases of powellite and hollandite that are the target hosts for radionuclides of Mo, Cs, and Rb, and iv) evaluating the durability and radiation stability of single and multi-phase ceramic waste forms.Two fabrication methods, including melting and crystallizing, and pressing and sintering, were used with the intent of studying phase evolution under various sintering conditions. An analysis of the XRD and SEM/EDS results indicates that the targeted crystalline phases of the FY11 compositions consisting of pyrochlore, perovskite, hollandite, zirconolite, and powellite were formed by both press and sinter and melt and crystallize processing methods. An evaluation of crystalline phase formation versus melt processing conditions revealed that hollandite, perovskite, zirconolite, and residual TiO 2 phases formed regardless of cooling rate, demonstrating the robust nature of this process for crystalline phase development.The multiphase ceramic composition CSLNTM-06 demonstrated good resistance to proton beam irradiation. Electron irradiation studies on the single phase CaMoO 4 (a component of the multiphase waste form) suggested that this material exhibits stability to 1000 years at anticipated self-irradiation doses (2×10 10 -2×10 11 Gy), but that its stability may be rate dependent, therefore limiting the activity of the waste for which it can be employed. Overall, these preliminary results indicate good radiation damage tolerance for the crystalline ceramic materials.The PCT results showed that, for all of the waste forms tested, the normalized release values for most of the elements measured, including all of the lanthanides and noble metals, were either very small or below the instrument detection limits. Elevated normalized release values were measured only for Cs, Mo, and Rb. It is difficult to draw further conclusions from these data until a benchmark material is developed for the PCT with this type of waste form. Calcined, simulated CS/LN/TM High Mo waste without additives had relatively low normalized release values for Cs, Mo, and Rb. A review of the chemical composition data for this sample showed that these elements were well retained after the calcination. Therefore, it will be useful to further characterize the calcined material to determine what form these elements are in after calcining. This, along with single phase...

show abstract

Inductive cold crucible melting of actinide-bearing murataite-based ceramics

Cited by 27 publications

References 9 publications

Single phase melt processed powellite (Ba,Ca)MoO4 for the immobilization of Mo-rich nuclear waste

Single phase melt processed powellite (Ba,Ca)MoO4 for the immobilization of Mo-rich nuclear waste

Extended Development Work to Validate a HLW Calcine Waste Form via INL's Cold Crucible Induction Melter

Development of Crystalline Ceramics for Immobilization of Advanced Fuel Cycle Reprocessing Wastes

Contact Info

Product

Resources

About