Article
Materials Science, Multidisciplinary
Peter G. Keech, Mehran Behazin, W. Jeffrey Binns, Scott Briggs
Summary: In 2012, the Nuclear Waste Management Organization developed a comprehensive proof test plan to evaluate the feasibility and safety of their copper-coated used fuel container for a proposed deep geological repository. Research focuses on evaluating various copper corrosion mechanisms and aims to refine a maximum copper corrosion allowance of <1.27 mm over a one million year emplacement.
MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION
(2021)
Article
Materials Science, Multidisciplinary
Wilfred Jeffrey Binns, Mehran Behazin, Scott Briggs, Peter G. Keech
Summary: The Nuclear Waste Management Organization has conducted a decade-long proof test plan to evaluate their copper-coated used fuel container and bentonite buffer box underground emplacement concept for a deep geological repository. The plan includes the development of new technologies and feasibility studies related to engineered barrier production, underground emplacement, and safety assessment. The work packages associated with corrosion performance evaluation of the used fuel container and copper corrosion in the Canadian DGR continue after the plan's completion, with attention given to local corrosion phenomena. The article provides an overview of these continued work packages, supporting a lifetime corrosion expectation of 270 micro-meters and an extreme upper bound of corrosion of 1204 micro-meters over one million years.
MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION
(2023)
Article
Materials Science, Multidisciplinary
Nicholas A. Senior, Taylor Martino, Jeff Binns, Peter Keech
Summary: This paper presents a study on the construction of the fuel container used in the Canadian deep geological repository and its adaptability to different groundwater chemistry to ensure the long-term integrity of the fuel container. The experiments found that under specific conditions, chloride or hydrogen sulphide may stimulate short-term corrosion behavior.
MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION
(2021)
Review
Materials Science, Multidisciplinary
David S. Hall, Mehran Behazin, W. Jeffrey Binns, Peter G. Keech
Summary: The review discusses the favoured design concept of permanent disposal of high level nuclear waste in containers and considers the corrosion processes that can affect these packages. It demonstrates the methodology used to calculate corrosion depth in a Canadian geological repository environment and suggests areas for future study. Various corrosion sub-allowances are considered, and the expected depth of corrosion over time is evaluated for a specific site condition.
PROGRESS IN MATERIALS SCIENCE
(2021)
Article
Materials Science, Multidisciplinary
Xiaoqi Yue, Per Malmberg, Elisa Isotahdon, Vilma Ratia-Hanby, Elina Huttunen-Saarivirta, Christofer Leygraf, Jinshan Pan
Summary: ToF-SIMS analysis was conducted to investigate the penetration of corrosive species containing H, S, O, and Cl into copper samples exposed to simulated groundwater with and without sulfide addition. Depth profiles revealed the extent of penetration, while 2D/3D images showed the local elemental distribution of the corrosive species at different depths inside copper. The results indicated that pre-oxidation had no effect on the penetration, but sulfide addition in groundwater and exposure at 60 degrees C significantly promoted it. This highlights the importance of conducting risk assessment for complex corrosion forms such as sulfide-induced embrittlement and cracking.
Article
Materials Science, Multidisciplinary
Mengnan Guo, Jian Chen, Taylor Martino, Christina Lilja, Johannes A. Johansson, Mehran Behazin, Wilfred J. Binns, Peter G. Keech, James J. Noel, David W. Shoesmith
Summary: The study revealed that the growth of copper sulfide films is controlled by the supply of SH- from the solution, and the morphology of the film depends on the type and concentration of anions present in the solution.
MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION
(2021)
Article
Materials Science, Multidisciplinary
Jian Chen, Xinran Pan, Taylor Martino, Christina Lilja, Mehran Behazin, Wilfred J. Binns, Peter G. Keech, James J. Noel, David W. Shoesmith
Summary: The corrosion of copper in chloride- and sulphate-containing solutions containing sulphide was studied. The structure and physical properties of the copper sulphide deposits were analyzed. Different factors, such as sulphide transport, chloride adsorption, and Cu-I transport, were found to influence the corrosion rates and the growth of copper sulphide deposits.
MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION
(2023)
Article
Economics
Ou Tang, Jakob Rehme, Pontus Cerin, Donald Huisingh
Summary: As renewable energy sources increase and nuclear power plants are decommissioned in Sweden, the electricity market experiences more fluctuations, highlighting the need to secure electricity supply. Hydrogen production has emerged as a potential source of income due to surplus electricity supply at low prices. Research on the feasibility of investing in hydrogen production at nuclear power plants under Swedish energy policy background reveals alternative opportunities for large-scale electricity production facilities.
Article
Materials Science, Multidisciplinary
A. M. Fedoseev, A. A. Bessonov, A. V. Sitanskaia, M. A. Volkov, A. G. Volkova, M. N. Sokolova, D. V. Ryabkov, K. K. Korchenkin, K. E. German
Summary: The preparation routes for ceramic-metal matrices, as well as their physical and chemical properties, were investigated. The surface morphology of CMM Tc-NpO2 and the leaching rate of different radionuclides were experimentally determined.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Geochemistry & Geophysics
Denis Strachan, James J. Neeway, Larry Pederson, Daniel K. Schreiber, Alexandre Mitroshkov, Zihua Zhu, Joseph V. Ryan
Summary: Understanding the mechanisms controlling the corrosion rate of nuclear waste glass is crucial for predicting radionuclide release. Results show that the release behavior of elements is influenced by their structural role in the glass and the role of water transport and ion exchange in long-term dissolution.
GEOCHIMICA ET COSMOCHIMICA ACTA
(2022)
Article
Electrochemistry
Mengnan Guo, Kevin Daub, Qingshan Dong, Fei Long, W. Jeffrey Binns, Mark R. Daymond, David W. Shoesmith, James J. Noel, Suraj Y. Persaud
Summary: The microstructure, corrosion rate, and electrochemical behavior of copper materials were investigated using electron backscatter diffraction and corrosion potential polarization measurements. The results showed that the cold spray copper had a heterogeneous microstructure and poor corrosion resistance, while the heat-treated cold spray copper had similar corrosion rate to electrodeposited copper and wrought copper.
JOURNAL OF THE ELECTROCHEMICAL SOCIETY
(2022)
Article
Materials Science, Multidisciplinary
Anna Dobkowska, Millicent Dayle H. Castillo, Joseph P. Turnbull, Sridhar Ramamurthy, Dmitrij Zagidulin, Desmond E. Moser, Mehran Behazin, Peter G. Keech, David W. Shoesmith, James J. Noel
Summary: The study focused on the corrosion behavior of coarse- and fine-grained copper materials in an aerated aqueous nitric acid solution. Crystallographic orientations greatly influenced the corrosion rate in coarse-grained materials, while grain boundary etching and grain boundary pores played a significant role in fine-grained materials.
Article
Geochemistry & Geophysics
Jin Ma, Marek Pekala, Peter Alt-Epping, Barbara Pastina, Susanna Maanoja, Paul Wersin
Summary: In this study, a 3D numerical model is developed to assess the corrosion depth and evolution of sulfide fluxes in the Finnish spent nuclear fuel repository concept. Long-term simulations predict a heterogeneous corrosion of the canister with a max. corrosion depth of 1.3 mm. The study also highlights the importance of organic carbon and Fe(III) oxide contents in the bentonite for the corrosion evolution.
APPLIED GEOCHEMISTRY
(2022)
Review
Nuclear Science & Technology
Tonni Agustiono Kurniawan, Mohd Hafiz Dzarfan Othman, Deepak Singh, Ram Avtar, Goh Hui Hwang, Tjandra Setiadi, Wai-hung Lo
Summary: Nuclear power is a sustainable energy option, but it generates radioactive waste during electricity production. Various technologies, including vitrification, partitioning and transmutation, pyro-processing, and deep geological repository, are reviewed for long-term storage of partially used nuclear fuel. While deep geological repository may be convenient and economical in the short-term, complete recycling of nuclear waste is considered the best option in the long-term.
ANNALS OF NUCLEAR ENERGY
(2022)
Article
Materials Science, Multidisciplinary
Joseph Turnbull, Ryan Szukalo, Dmitrij Zagidulin, Mark Biesinger, David Shoesmith
Summary: The study focused on determining the kinetics of nitrate and oxygen reduction and elucidating the synergistic relationship between the two processes, showing that oxygen reduction is the dominant cathodic reaction with the oxidation of copper(I) to copper(II) promoted by nitrate.
MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION
(2021)
Article
Materials Science, Multidisciplinary
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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)