4.7 Article

Microstructure and leaching durability of glass composite wasteforms for spent clinoptilolite immobilisation

期刊

JOURNAL OF NUCLEAR MATERIALS
卷 372, 期 2-3, 页码 358-366

出版社

ELSEVIER
DOI: 10.1016/j.jnucmat.2007.04.047

关键词

-

向作者/读者索取更多资源

Simulated spent Cs-clinoptilolite waste was immobilised in a monolithic glass composite material (GCM) produced by a pressureless sintering at 750 degrees C for 2 h duration. The effects of waste loading from 1: 1 up to 1: 10 glass to waste volume ratio (37 up to 88 wt%) on the GCM wasteform microstructure and leaching properties were analysed. The open porosity ranged between 0.84 and similar to 13.2 % for the highest waste load. Significant changes occurred in the microstructure, phases present and wasteform durability at different waste loading. At waste loading up to 73 wt% of spent clinoptilolite, the GCM microstructure consists of several crystalline phases (clinoptilolite, socialite, wollastonite and CsCl) that were fully encapsulated by a glass matrix. This leads to a low normalized leaching rate of Cs (remaining below 6.35 x 10(-6) g/cm(2) day in a GCM with 73 wt% waste) during a leaching test for 7 days conducted using ASTM C1220-98. In GCM's with waste loading exceeding 73 wt%, the crystalline phases present (clinoptilolite and CsCl) were not fully encapsulated by the glass matrix hence the normalized leaching rate of Cs was as high as 9.06 x 10(-4) g/cm(2) day at waste loading of >= 80 wt%. (C) 2007 Elsevier B.V. All rights reserved.

作者

我是这篇论文的作者
点击您的名字以认领此论文并将其添加到您的个人资料中。

评论

主要评分

4.7
评分不足

次要评分

新颖性
-
重要性
-
科学严谨性
-
评价这篇论文

推荐

Article Materials Science, Ceramics

Atomistic modeling approach to the thermodynamics of sodium silicate glasses

Paul C. M. Fossati, Thomas A. Mellan, Navaratnarajah Kuganathan, William E. Lee

Summary: A study was conducted on the vibration modes and thermodynamical properties of amorphous sodium silicate using atomic-scale models and considering different Na2O concentrations. The potentials used showed the ability to describe various oxides, suggesting potential for studying more complex glasses in the future.

JOURNAL OF THE AMERICAN CERAMIC SOCIETY (2021)

Article Materials Science, Ceramics

Interface properties of Ti3SiC2/Al2O3 ceramics: Combined experiments and first-principles calculations

Jun Ji, Liu Zhang, Jinman Yu, William E. Lee, Simon C. Middleburgh, Dechun Li, Xuye Wang, Qinggang Li, Zhi Wang, Guopu Shi, Fei Chen

Summary: The synthesis, characterization, and first-principles calculations of Ti3SiC2/Al2O3 ceramics were investigated. The purity of the composite ceramics was confirmed through X-ray diffraction measurements. The stability and intercrystalline strengthening of Ti3SiC2/Al2O3 composite ceramics were found to be influenced by the terminations of Ti3SiC2 and Al2O3 crystals, particularly the attraction between coordinatively unsaturated Ti and O atoms on their interface.

CERAMICS INTERNATIONAL (2021)

Article Nuclear Science & Technology

Performance and economic assessment of enriched gadolinia burnable absorbers

M. J. Bolukbasi, S. C. Middleburgh, M. Dahlfors, W. E. Lee

Summary: In this study, fuel assemblies using gadolinium oxide enriched with 157Gd isotope were modelled and compared to natural Gd based absorber. The use of enriched Gd isotopes in the fuel eliminates residual reactivity caused by natural gadolinium oxide and allows similar reactivity properties with less burnable absorber. The financial cost of incorporating enriched Gd isotopes into nuclear fuel has also been estimated.

PROGRESS IN NUCLEAR ENERGY (2021)

Article Nuclear Science & Technology

Utilizing neutronics modelling to predict changing Pu ratios in UO2 in the presence of Th

L. J. Evitts, M. R. Gilbert, S. C. Middleburgh, W. E. Lee, M. Dahlfors

Summary: The presence of thorium in UO2 fuel rods can significantly impact the ratios of plutonium isotopes. As burnup and thorium content increase, the 242Pu/239Pu ratio may rise by as much as 3.5% in extreme cases.

PROGRESS IN NUCLEAR ENERGY (2021)

Article Materials Science, Multidisciplinary

Diffusion in doped and undoped amorphous zirconia

Megan W. Owen, Michael J. D. Rushton, Lee J. Evitts, Antoine Claisse, Mattias Puide, William E. Lee, Simon C. Middleburgh

Summary: Grain boundaries in ZrO2 can serve as pathways for species like oxygen and hydrogen, influencing corrosion. Impurities and alloying elements can lead to highly-doped grain boundaries with amorphous structures, which shows increased oxygen diffusivity compared to undoped crystalline systems.

JOURNAL OF NUCLEAR MATERIALS (2021)

Article Nanoscience & Nanotechnology

HfB2 ceramic polycrystals: A low-temperature metal-like ceramic at high temperatures?

Eugenio Zapata-Solvas, Bibi Malmal Moshtaghioun, Diego Gomez-Garcia, Arturo Dominguez-Rodriguez, William E. Lee

Summary: This paper examines the mechanical response of hafnium diboride at different temperatures and reveals that it exhibits metal mechanical behavior.

SCRIPTA MATERIALIA (2021)

Article Chemistry, Physical

The accommodation of lithium in bulk ZrO2

Gareth F. Stephens, Yan Ren Than, William Neilson, Lee J. Evitts, Mark R. Wenman, Samuel T. Murphy, Robin W. Grimes, Aidan Cole-Baker, Susan Ortner, Natasha Gotham, Michael J. D. Rushton, William E. Lee, Simon C. Middleburgh

Summary: The research investigated the accommodation mechanisms for Li in ZrO2 using density functional theory, finding that the solubility of Li into ZrO2 is very low, indicating it is unlikely to be the cause for accelerated corrosion under equilibrium conditions.

SOLID STATE IONICS (2021)

Article Materials Science, Multidisciplinary

Hydrogen accommodation in the TiZrNbHfTa high entropy alloy

C. M. Moore, J. A. Wilson, M. J. D. Rushton, W. E. Lee, J. O. Astbury, S. C. Middleburgh

Summary: The atomic-scale behavior of a high entropy alloy and its hydrides during hydrogen absorption has been simulated using density functional theory, revealing the promotion of vacancy formation by hydrogen and proposing a model for hydride decomposition. Phase transformations were observed in different arrangements of the hydride structure under specific conditions.

ACTA MATERIALIA (2022)

Article Materials Science, Ceramics

Fabrication and characterisation of single-phase Hf2Al4C5 ceramics

Doni Daniel Jayaseelan, S. Pramana, S. Grasso, Y. Bai, S. Skinner, M. J. Reece, W. E. Lee

Summary: In this study, single-phase Hf2Al4C5 ternary carbide was fabricated using pressure assisted sintering techniques and its properties were investigated at different temperatures. The results showed that Hf2Al4C5 started to form at relatively low temperatures and fully formed after reactive sintering for a certain period of time. The thermal conductivity of Hf2Al4C5 was measured to be good at high temperatures. The oxidation study revealed that Hf2Al4C5 exhibited good oxidation resistance at high temperatures and had favorable interface bonding characteristics.

JOURNAL OF THE EUROPEAN CERAMIC SOCIETY (2022)

Article Energy & Fuels

Predicting the thermal expansion of body-centred cubic (BCC) high entropy alloys in the Mo-Nb-Ta-Ti-W system

Jack A. Wilson, Lee J. Evitts, Alberto Fraile, Roy E. Wilson, Michael J. D. Rushton, David T. Goddard, William E. Lee, Simon C. Middleburgh

Summary: In this study, the thermal expansion behavior of equiatomic alloys in the Mo-Nb-Ta-Ti-W system was investigated using atomic-scale modeling techniques. The results showed that these techniques can reliably predict the thermal expansion behavior of high entropy alloys and concentrated solid solutions.

JOURNAL OF PHYSICS-ENERGY (2022)

Article Nuclear Science & Technology

Effect of ZrB2 and UB2 Discrete Burnable Absorber Pins on fuel reactivity

Mustafa J. Bolukbasi, Simon C. Middleburgh, Scott Vrtiska, William E. Lee

Summary: Improvements in fuel efficiency and economy are crucial for nuclear power reactors. Burnable absorbers (BA) are being developed to enhance fuel cycle flexibility and mitigate performance drawbacks. This study investigates a novel concept - Discrete Burnable Absorber Pins (DBAP) containing ZrB2 and UB2, which show great potential for fuel efficiency and economy. It is observed that the use of DBAP leads to increased reactivity at the end of fuel life due to changes in Pu-239 breeding near the BA.

PROGRESS IN NUCLEAR ENERGY (2022)

Editorial Material Energy & Fuels

Materials challenges for successful roll-out of commercial fusion reactors

Amanda Quadling, William Edward Lee, Jack Astbury

Summary: This paper introduces a special issue of the Journal of Physics: Energy, compiled by the UK fusion community, discussing the key challenges in the materials aspect of fusion reactors and their successful roll-out. These challenges include resilience to tritium, transmutation, and neutron bombardment, suitable irradiation strategies for damage studies, and defining guidance for material safety and waste management in the evolving regulatory era.

JOURNAL OF PHYSICS-ENERGY (2022)

Article Materials Science, Ceramics

Addressing high processing temperatures in reactive melt infiltration for multiphase ceramic composites

Phylis Makurunje, Simon C. Middleburgh, William E. Lee

Summary: This review discusses various approaches to address the high processing temperatures required in reactive melt infiltration (RMI) processing of modern multiphase ceramic matrix composites (CMCs). It focuses on using immiscible phases, miscible phases, silicide phases, and/or silicide eutectics to lower the temperature requirement for RMI, optimizing the composition of incorporated phases, minimizing damage to reinforcing phases, utilizing rapid heating techniques, and developing in situ real-time monitoring systems. Future opportunities include integrating additive manufacturing with RMI, utilizing process modeling, and applying in situ and in operando characterization techniques.

JOURNAL OF THE EUROPEAN CERAMIC SOCIETY (2023)

Article Materials Science, Multidisciplinary

Diffusion in undoped and Cr-doped amorphous UO 2

Megan W. Owen, Michael W. D. Cooper, Michael J. D. Rushton, Antoine Claisse, William E. Lee, Simon C. Middleburgh

Summary: UO 2 fuel pellets are often doped with chromium oxide to improve their properties. The low solubility of chromium in UO 2 can lead to segregation of Cr ions to the grain boundary, affecting the material and operational properties of the fuel pellet. This study investigates the structure and diffusion behavior of undoped and Cr doped UO 2 systems using molecular dynamics methods, and highlights the importance of additives in retaining fission products and other migratory species.

JOURNAL OF NUCLEAR MATERIALS (2023)

Article Nanoscience & Nanotechnology

Modelling the impact of configurational entropy on the stability of amorphous SiO2

Megan W. Owen, Michael J. D. Rushton, Michael W. D. Cooper, E. M. Ghardi, Antoine Claisse, William E. Lee, Simon C. Middleburgh

Summary: Configurational entropy has been calculated to determine its role in stabilizing the amorphous structure of SiO2. Various atomic scale modeling methods were used to assess the structures of crystalline and amorphous SiO2, and the associated configurational entropy was computed at different temperatures. Together with the enthalpy terms from density functional theory, a reliable method for evaluating the stability of crystalline and amorphous structures has been proposed for future studies on dopants, glass forming additives, and radiation damage. Future work will consider the contribution of vibrational entropy to complete the assessment of amorphization.

SCRIPTA MATERIALIA (2023)

Article Materials Science, Multidisciplinary

H dissolution and desorption near He-V complexes in W surfaces with different orientations

Liuming Wei, Jingwen Li, Yonggang Li, Qirong Zheng, Fan Cheng, Chuanguo Zhang, Jingyu Li, Gaofeng Zhao, Zhi Zeng

Summary: This study investigates the influence of He-V complexes on H behaviors on different W surfaces using DFT calculations. The results show that H dissolution is most difficult but H trapping is easiest on the W (110) surface, while the opposite is true on the W (111) surface. Moreover, the presence of He-V complexes increases the difficulty of H diffusion from bulk to surface and desorption.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Effect of deposition parameters on characteristics and oxidation behavior of magnetron sputtered Cr coatings

Yan Meng, Song Zeng, Chen Chen, Chaowen Zhu, Huahai Shen, Xiaosong Zhou, Xiaochun Han

Summary: The characteristics of magnetron sputtered Cr coatings vary with different temperature, bias voltage, and pressure. Coatings with random orientation, good crystallinity, and small grain size exhibit favorable oxidation behavior, while coatings with strong (200) texture, poor crystallinity, and large grains have many intrinsic defects that are detrimental to the protection property of the Cr coatings.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Automated analysis of grain morphology in TEM images using convolutional neural network with CHAC algorithm

Xinyuan Xu, Zefeng Yu, Wei-Ying Chen, Aiping Chen, Arthur Motta, Xing Wang

Summary: This study presents an automated approach for characterizing grain morphology in TEM images recorded during ion irradiation. By combining a machine learning model and a computer vision algorithm, comparable results to human analysis can be achieved with significantly reduced analysis time. Researchers can train their own models following the procedures described in this study to automate grain morphology analysis of their own TEM images.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Model development for oxidation and degradation behavior of accident tolerant Cr coating on Zr alloy cladding under high temperature steam atmosphere

Shihao Wu, Dong Wang, Yapei Zhang, Koji Okamoto, Marco Pellegrini, Wenxi Tian, Suizheng Qiu, G. H. Su

Summary: The oxidation and degradation mechanisms of Cr coating on Zr alloy cladding under high temperature steam atmosphere are summarized, and a mathematical analysis model is established to predict the changes in coating thickness. The model is applied in the analysis of structure evolution under different conditions.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Numerical and experimental development of cupronickel filler brazed joints for divertor and first wall components in DEMO fusion reactor

V. Diaz-Mena, J. de Prado, M. Roldan, I. Izaguirre, M. Sanchez, M. Rieth, A. Urena

Summary: The brazeability of a cupronickel alloy was evaluated as a filler alloy for high-temperature joining of tungsten to steel. The study investigated the brazing conditions and the impact of the selected filler on the joint quality using numerical software. The results showed different metallurgical interactions and diffusion phenomena between the filler alloy and the base materials at different temperatures. The study emphasized the importance of selecting a suitable filler to mitigate residual stresses in the joints.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Defect-specific strength factors and superposition model for predicting strengthening of ion irradiated Fe18Cr alloy

Pengcheng Zhu, Yajie Zhao, Yan-Ru Lin, Jean Henry, Steven J. Zinkle

Summary: This study investigates the effect of heavy-ion irradiation on radiation hardening in high-purity binary alloy Fe18Cr. Nanoindentation testing and high-quality TEM imaging were conducted to extract hardness and microstructure information. The strength factor was accurately calculated based on the detailed TEM characterization of irradiated microstructures, and a refined hardening superposition method was applied to quantify the mechanical properties of ion-irradiated materials.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Synthesis and characterization of sodium-aluminophosphate based glass-ceramics containing NZP phase for HLW immobilization

Bin Wu, Haixia Ning, Hanzhen Zhu, Jianjun Chen, Kang Wang, Daiyu Zhang, Fu Wang, Qilong Liao

Summary: This study discusses the effects of ZrO2 and B2O3 on the phase composition and properties of SAP-based glass-ceramics. The results show that ZrO2 addition improves the formation of NZP phase while restricting the crystallization of AlPO4 phases. The correct ratios of ZrO2 and B2O3 allow only the formation of NZP phase within the SAP glass.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

High temperature oxidation of cold spray Cr-coated accident tolerant zirconium-alloy cladding with Nb diffusion barrier layer

Hwasung Yeom, Greg Johnson, Benjamin Maier, Tyler Dabney, Kumar Sridharan

Summary: Cr-Nb bilayer coatings were developed using cold spray deposition to improve the limiting operational temperature of Cr-coated Zr-alloy system. The coatings exhibited outstanding oxidation resistance at high temperatures and formed continuous intermetallic compound layers at the interfaces.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Irradiation creep measurement and microstructural analysis of chromium nitride-coated zirconium alloy using pressurized tubes

Padhraic L. Mulligan, Andrew T. Nelson, Chad M. Parish, Patrick A. Champlin, Xiang Chen, Daniel Morrall, Jason M. Harp

Summary: Environmental barrier coatings are being developed to reduce oxidation and embrittlement in Zr-based materials. Chromium nitride is a candidate for this application, but understanding its impact on irradiation-induced creep and microstructure is critical.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Determination of impurity distribution in IG-11/110 nuclear graphite using TOF-SIMS

Dexuan Yan, Xinlei Cao, Ke Shen

Summary: This study investigated the purification mechanism of polycrystalline graphite by comparing IG-11 graphite with IG-110 nuclear grade graphite. The analysis revealed that metallic impurities in IG-11 were primarily segregated within graphite porosities, while IG-110 demonstrated a significant reduction in impurities. This research contributes to the development of innovative graphite purification techniques for greater purity and stronger oxidation resistance.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Study of multi-pebble oxidation process in high-temperature gas-cooled reactor

Wei Xu, Wei Peng, Lei Shi, Qi Sun

Summary: This paper investigates the oxidation and shape evolution of matrix graphite in high temperature gas-cooled reactors during air-ingress accidents. A reaction kinetics model is established and computational fluid dynamics with a dynamic mesh method is used to simulate the oxidation process. The results show that the geometric shape of graphite changes significantly with increasing flow rate, and the graphite pebbles tend to form a structure with a narrow front and wide tail.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Synthesis and characterization of super occluded LiCl-KCl in zeolite-4A as a chloride salt waste form intermediate

Allison Harward, Casey Elliott, Michael Shaltry, Krista Carlson, Tae-Sic Yoo, Guy Fredrickson, Michael Patterson, Michael F. Simpson

Summary: This paper investigates the hygroscopic properties of eutectic LiCl-KCl absorbed into zeolite-4A. The study finds that water absorption and corrosion worsen with increasing salt loading. It also suggests that the salt can be stored in a non-inert atmosphere for a certain period of time.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Hermeticity of SiC/SiC composite and monolithic SiC tubes irradiated under radial high-heat flux

Takaaki Koyanagi, Xunxiang Hu, Christian M. Petrie, Gyanender Singh, Caen Ang, Christian P. Deck, Weon-Ju Kim, Daejong Kim, James Braun, Yutai Katoh

Summary: This study provides critical experimental data on the effects of irradiation on the hermeticity of SiC composite cladding, finding that irradiation can cause a decrease in hermeticity and cracking, and coating the outer surface can mitigate the cracking issue.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Theoretical estimation of multiple hydrogen isotope content in metal layers slowly co-deposited from plasmas

S. Krat, A. Prishvitsyn, Yu. Gasparyan

Summary: This study proposes a probabilistic and diffusion-based model to describe the co-deposition of multiple hydrogen isotopes with slowly grown metal layers. The model calculates the relative concentrations of different hydrogen isotopes in the co-deposited metal layers. It is found that if hydrogen isotopes have different detrapping energies, only the isotope with the highest detrapping energy shows a monotonic decrease in concentration with deposition temperature. Furthermore, the study evaluates the uncertainty of tritium concentration in the co-deposited layer based on the uncertainty in detrapping energy of tritium and deuterium, predicting a >10% tritium concentration uncertainty for a 0.01 eV difference.

JOURNAL OF NUCLEAR MATERIALS (2024)

Article Materials Science, Multidisciplinary

Computational study of thermophysical properties of cerium doped UO2: Effect of oxidation states

Tijo Vazhappilly, Arup Kumar Pathak

Summary: This study investigates the effect of Ce atom substitution in UO2 on its thermophysical properties using density functional theory. The results show that the Ce substitution levels and the oxidation state of Ce/U atoms strongly influence the band structure and specific heat capacity of the UO2 lattice. These findings provide important insights into the fuel properties of UO2 under reactor conditions.

JOURNAL OF NUCLEAR MATERIALS (2024)