4.7 Article

Amorphisation of boron carbide under slow heavy ion irradiation

Journal

JOURNAL OF NUCLEAR MATERIALS
Volume 476, Issue -, Pages 198-204

Publisher

ELSEVIER
DOI: 10.1016/j.jnucmat.2016.04.030

Keywords

Boron carbide; Amorphisation; Ion irradiation; TEM; Raman

Funding

  1. federative NEEDS research program

Ask authors/readers for more resources

Boron carbide B4C is widely used as a neutron absorber in nuclear plants. Most of the post-irradiation examinations have shown that the structure of the material remains crystalline, in spite of very high atomic displacement rates. Here, we have irradiated B4C samples with 4 MeV Au ions with different fluences at room temperature. Transmission electron microscopy (TEM) and Raman spectroscopy have been performed. The Raman analyses show a high structural disorder at low fluence, around 10-2 displacements per atoms (dpa). However, the TEM observations show that the material remains crystalline up to a few dpa. At high fluence, small amorphous areas a few nanometers large appear in the damaged zone but the long range order is preserved. Moreover, the size and density of the amorphous zones do not significantly grow when the damage increases. On the other hand, full amorphisation is observed in the implanted zone at a Au concentration of about 0.0005. It can be inferred from those results that short range and long range damages arise at highly different fluences, that heavy ions implantation has drastic effects on the structure stability and that in this material self-healing mechanisms are active in the damaged zone. (C) 2016 Elsevier B.V. All rights reserved.

Authors

I am an author on this paper
Click your name to claim this paper and add it to your profile.

Reviews

Primary Rating

4.7
Not enough ratings

Secondary Ratings

Novelty
-
Significance
-
Scientific rigor
-
Rate this paper

Recommended

Article Physics, Applied

Raman spectroscopy study of damage induced in cerium dioxide by swift heavy ion irradiations

Jean-Marc Costantini, Sandrine Miro, Gaelle Gutierrez, Kazuhiro Yasuda, Seiya Takaki, Norito Ishikawa, Marcel Toulemonde

JOURNAL OF APPLIED PHYSICS (2017)

Article Materials Science, Multidisciplinary

Micro-Raman analysis of the fuel-cladding interface in a high burnup PWR fuel rod

Clement Ciszak, Michel Mermoux, Sandrine Miro, Gaelle Gutierrez, Frederic Lepretre, Ioana Popa, Karine Hanifi, Isabelle Zacharie-Aubrun, Laurent Fayette, Sebastien Chevalier

JOURNAL OF NUCLEAR MATERIALS (2017)

Article Instruments & Instrumentation

Ion beam modification of zinc white pigment characterized by ex situ and in situ μ-Raman and XPS

L. Beck, P. C. Gutierrez, S. Miro, F. Miserque

NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS (2017)

Article Materials Science, Multidisciplinary

Damage induced in garnets by heavy ion irradiations: a study by optical spectroscopies

Jean-Marc Costantini, Sandrine Miro, Gerald Lelong, Maxime Guillaumet, Marcel Toulemonde

PHILOSOPHICAL MAGAZINE (2018)

Article Physics, Applied

Defects induced in cerium dioxide single crystals by electron irradiation

Jean-Marc Costantini, Sandrine Miro, Nadia Touati, Laurent Binet, Gilles Wallez, Gerald Lelong, Maxime Guillaumet, William J. Weber

JOURNAL OF APPLIED PHYSICS (2018)

Article Materials Science, Multidisciplinary

Investigating the role of irradiation defects during UO2 oxidative dissolution

R. Mohun, L. Desgranges, A. Canizares, N. Raimboux, F. Duval, R. Omnee, C. Jegou, S. Miro, P. Simon

JOURNAL OF NUCLEAR MATERIALS (2018)

Article Instruments & Instrumentation

Effect of ballistic damage in UO2 samples under ion beam irradiations studied by in situ Raman spectroscopy

G. Gutierrez, C. Onofri, S. Miro, M. Bricout, F. Lepretre

NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS (2018)

Article Instruments & Instrumentation

Raman investigation of ion irradiated TiC and ZrC

S. Pellegrino, P. Trocellier, L. Thome, S. Miro, J-M. Costantini, E. Jouanny

NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS (2019)

Article Materials Science, Multidisciplinary

The mechanisms of alteration of a homogeneous U0.73PU0.27O2 MOx fuel under alpha radiolysis of water

Valentin Kerleguer, Christophe Jegou, Laurent De Windt, Veronique Broudic, Gauthier Jouan, Sandrine Miro, Florent Tocino, Christelle Martin

JOURNAL OF NUCLEAR MATERIALS (2020)

Article Materials Science, Multidisciplinary

Structural modifications of boron carbide irradiated by swift heavy

Y. Pipon, G. Victor, N. Moncoffre, G. Gutierrez, S. Miro, T. Douillard, O. Rapaud, N. Pradeilles, P. Sainsot, N. Toulhoat, M. Toulemonde

Summary: The behavior of boron carbide (B4C) under irradiation, particularly in relation to high electronic stopping powers (Se), has been extensively studied to predict its longevity in future nuclear fission reactors. Experimental results showed that under high Se values, significant surface damage and bulk amorphization occur in B4C, indicating the importance of understanding these effects for predicting material performance under irradiation.

JOURNAL OF NUCLEAR MATERIALS (2021)

Article Chemistry, Physical

Studtite Formation Assessed by Raman Spectroscopy and 18O Isotopic Labeling during the Oxidative Dissolution of a MOX Fuel

Lola Sarrasin, Sandrine Miro, Christophe Jegou, Magaly Tribet, Veronique Broudic, Caroline Marques, Sylvain Peuget

Summary: The formation of studtite was studied using isotopic labeling during oxidative dissolution of a MIMAS MOX fuel disk in aerated water enriched in O-18, showing different enrichments of O-18 in the uranyl and peroxide bonds of studtite. Additionally, the influence of MOX MIMAS heterogeneous microstructure and chemistry was observed with preferential dissolution of UO2 grains and stability of Pu-rich areas during the experiment.

JOURNAL OF PHYSICAL CHEMISTRY C (2021)

Article Materials Science, Multidisciplinary

Impact of complex irradiation scenarios on the structure and the properties of the International Simple Glass

C. Gillet, S. Szenknect, M. Tribet, S. Miro, T. Charpentier, M. Odorico, S. Peuget

Summary: This study investigates the coupling effect between electron irradiation and Au irradiation on the structure and properties of ISG glass. The experimental results show that the changes induced by Au irradiation are similar to those induced by sequential irradiation, while electron irradiation has a smaller impact on ISG glass. Furthermore, the hardness and density changes of ISG glass are similar to SON68 glass under similar irradiation conditions.

JOURNAL OF NUCLEAR MATERIALS (2022)

Article Materials Science, Multidisciplinary

Monitoring of alpha-decay radiation damage in a 241Am-doped glass-ceramic material

S. Miro, N. Sellami, P. Chevreux, G. Jouan, M. Tribet, C. Jegou, I. Bardez-Giboire, S. Peuget

Summary: The evolution of a 241 Am doped aluminoborosilicate glass-ceramic under alpha-decay radiation was investigated. The excess of solubility limit led to the formation of apatite-like silicate crystals with a hexagonal morphology. Structural and microstructural changes were observed over 8 years, including radiation-induced amorphization and modification of connectivity in the crystals. The transformation from crystalline to amorphous state was accompanied by volume increase and decohesion from the glassy matrix.

JOURNAL OF NUCLEAR MATERIALS (2023)

Article Materials Science, Multidisciplinary

Radiations effects in ISG glass: from structural changes to long-term aqueous behavior

Sylvain Peuget, Magaly Tribet, Sarah Mougnaud, Sandrine Miro, Christophe Jegou

NPJ MATERIALS DEGRADATION (2018)

Article Physics, Applied

FTIR study of silicon carbide amorphization by heavy ion irradiations

Jean-Marc Costantini, Sandrine Miro, Olivier Pluchery

JOURNAL OF PHYSICS D-APPLIED PHYSICS (2017)

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)