Article
Nuclear Science & Technology
D. Terentyev, W. Leysen, N. Castin, C. C. Chang, G. Kennedy, A. Stankovskiy, L. Fiorito
Summary: The Belgian Nuclear Research Centre is developing MYRRHA, a subcritical accelerator driven system ignited by a superconducting linear proton accelerator. The implementation will be done in phases, with the first phase including the deployment of a 100 MeV proton accelerator and fusion-dedicated research facilities. The conceptual design of the facilities and the equivalence of irradiation conditions with other material test facilities are discussed.
FUSION ENGINEERING AND DESIGN
(2023)
Article
Chemistry, Multidisciplinary
Xu Zhang, Xiang Zhang, Pulickel M. Ajayan, Jianguo Wen, Horacio D. Espinosa
Summary: The annihilation of vacancy clusters in monolayer molybdenum diselenide (MoSe2) under electron beam irradiation is achieved by diffusion of vacancies towards the free edge. It is shown that electron beam irradiation and pre-stress in the suspended MoSe2 monolayer are necessary for vacancies to overcome energy barriers for diffusion. This new mechanism of vacancy healing in 2D materials expands the capability of electron beam in defect engineering and tuning the properties of 2D materials for applications.
Article
Materials Science, Multidisciplinary
R. Boffy, L. Martel, R. Schweins, J. Somers, J. Beaucour, F. J. Bermejo
Summary: The internal structure of several alkali-borosilicate glasses when exposed to a high thermal neutron flux was studied, with different glasses showing varying resistance to irradiation. Experimental tools like Nuclear Magnetic Resonance (NMR) and Small Angle Neutron Scattering (SANS) were used for structural analysis, revealing the possibility of phase segregation in a zinc-alkali-borosilicate.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Chemistry, Physical
Lokesh Goel, P. S. Ghosh, K. V. Mani Krishna, A. Arya, R. Tewari
Summary: In-situ TEM investigations were conducted to study the evolution of the omega phase in Zr-20Nb alloy under the influence of 2 MeV electrons at different temperatures. The results showed continuous shifting of the peak intensity maxima during the transformation, which can be explained by the existence of sub-units of omega phase predicted through Monte-Carlo simulations. Simulations based on density functional theory also predicted an increasing tendency of omega phase formation with decreasing Nb concentration in the alloy. It was found that the omega phase destabilized after a certain duration of irradiation, attributed to the increased vacancy concentration induced by 2 MeV electrons.
JOURNAL OF ALLOYS AND COMPOUNDS
(2022)
Article
Chemistry, Multidisciplinary
Sadegh Ghaderzadeh, Silvan Kretschmer, Mahdi Ghorbani-Asl, Gregor Hlawacek, Arkady V. Krasheninnikov
Summary: Controlled ion irradiation in hexagonal boron nitride (h-BN) can add new functionalities and develop optical quantum applications. The study on vacancy creation under ion irradiation can guide experiments aiming at creating specific types of defects for various applications.
Article
Biochemical Research Methods
Kyle L. Naughton, James Q. Boedicker
Summary: Microbes are highly efficient in synthesizing nanomaterials, and synthetic biologists have successfully engineered a variety of functional nanomaterials using genetic tools. Theoretical approaches can simulate biogenic nanomaterial synthesis, providing guidance for future experiments. The combination of experimental and theoretical approaches shows promise in advancing microbial nanomaterial synthesis.
ACS SYNTHETIC BIOLOGY
(2021)
Article
Chemistry, Inorganic & Nuclear
A. M. Akhanov, M. T. Aitkulov, D. S. Sairanbayev, Sh. Kh Gizatulin, N. K. Romanova, A. A. Shaimerdenov, Y. V. Chikhray, Zh Ualzhanov, T. K. Zholdybayev
Summary: This study justifies the design calculations of irradiation capsules for efficient coloring of topaz in a WWR-K reactor. The influence of various radiation screens on the activation of impurities in topaz is considered. Neutron analysis shows that a sandwich screen composed of boron carbide and tantalum is optimal for topaz irradiation. Thermal analysis indicates the importance of circulation between topaz during irradiation to reduce the temperature.
APPLIED RADIATION AND ISOTOPES
(2022)
Article
Materials Science, Ceramics
Zhixue Qu, Chuanjin Yu, Yitong Wei, Xiping Su, Aibing Du
Summary: This study quantitatively evaluated the contributions of various irradiation-induced defects in boron carbide and proposed a theoretical model without adjustable parameters based on phonon scattering theory. The model was validated using experimental data to predict the thermal conductivity variation under irradiation. Results suggest that substitutional defects and Frenkel defect pairs, rather than helium bubbles, play determining roles in the abrupt degradation of thermal conductivity during burnup.
JOURNAL OF ADVANCED CERAMICS
(2022)
Article
Nuclear Science & Technology
Abdullah G. Weiss, Moiz Butt, Pavel Tsvetkov, Mark L. Kimber, Sean M. McDeavitt
Summary: A new methodology for designing neutron shields and selecting moderators using a set of generalized metrics is presented in this study. The metrics were derived from multiple simulations and accurately track the exponential energy decrement of neutrons in media. This approach allows for streamlined analysis of complex neutron attenuating media.
ANNALS OF NUCLEAR ENERGY
(2021)
Article
Materials Science, Multidisciplinary
Siwei Zhang, Size Chen, Dan Xiao, Yong Zhang, Yongju Sun, Taosheng Li
Summary: This study proves the effectiveness of Tritium-Mg targets in improving neutron yield, with MgD2 targets exhibiting better thermal stability and neutron yield. However, the neutron yield with MgD2 targets is significantly attenuated due to irradiation damage.
Article
Materials Science, Multidisciplinary
Luca Reali, Mark R. Gilbert, Max Boleininger, Sergei L. Dudarev
Summary: Neutrons interacting with atomic nuclei in fusion reactors generate a y-photon flux and intense flux of high-energy electrons in materials. These fluxes have implications for crystal defects, plasma stability, and reactor component heating. Although highly resolved numerical calculations of fluxes on a reactor scale are not feasible, estimates based on Boltzmann's transport equation can provide insights into photon and electron generation in different materials and irradiation conditions.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Materials Science, Multidisciplinary
Elchin M. Huseynov, Efsane A. Huseynova
Summary: The band structure of nanocrystalline anatase (TiO2) particles was investigated using FTIR spectroscopy before and after neutron irradiation. The changes in peak values and the appearance of new peaks in the infrared absorption spectra were explained, revealing the structural changes on the nanoparticle surface and the effects of neutron irradiation on the surface activity and crystalline structure of the nanocrystals.
Article
Engineering, Aerospace
Chih-Yung Huang, Zih-Chen Lin, Chao-Yu Chen
Summary: The study designed a microsupersonic wind tunnel and conducted numerical and experimental analysis on its performance. By adding a plenum chamber and a reservoir, steady pressure conditions were ensured during experiments. The results showed that local high- and low-pressure regions could still be observed through pressure-sensitive paint (PSP) measurements under different pressure conditions.
Article
Materials Science, Multidisciplinary
Yan Yu, Yang Yu
Summary: This study investigates the irradiation damage process of NiCoCrFe high-entropy alloy (HEA) using molecular dynamics simulations. The results show that the distribution of irradiation defects in NiCoCrFe is relatively scattered, and higher energy irradiation leads to smaller clusters and fewer dislocations. As a result, the mechanical properties of NiCoCrFe decline less when applying tensile stress compared to Ni. These findings demonstrate the radiation resistance of high-entropy alloys and the stability of the mechanical properties of NiCoCrFe under high-energy irradiation.
MATERIALS TODAY COMMUNICATIONS
(2022)
Article
Physics, Multidisciplinary
Miyuki Yajima, Yuji Hatano, Vladimir Kh Alimov, Takeshi Toyama, Tatsuya Kuwabara, Thomas Schwarz-Selinger, Yasuhisa Oya, Alexander Spitsyn, Noriyasu Ohno
Summary: The study focused on hydrogen isotope trapping at lattice defects in neutron-irradiated tungsten. Characterization of defects revealed the presence of dislocations, monovacancies, and relatively large vacancy clusters which trapped deuterium atoms with different values of binding energy. Dependence of deuterium retention on plasma exposure temperature and damage level was observed, showing that weaker traps with smaller binding energy increased more significantly with damage level.
Review
Materials Science, Multidisciplinary
D. J. M. King, A. J. Knowles, D. Bowden, M. R. Wenman, S. Capp, M. Gorley, J. Shimwell, L. Packer, M. R. Gilbert, A. Harte
Summary: This review discusses the potential of current Zr alloys and advanced Zr alloys to meet the requirements of structural materials in fusion reactors. While current commercial Zr alloys can be used in water-cooled breeder blanket designs, they fail to meet the high temperature strength and thermal creep requirements for breeder blankets operating at higher temperatures. Higher order Zr alloys show promise in achieving the necessary high temperature strength, ductility, and low thermal neutron cross-section, but there is limited data and uncertainty regarding their structural performance and microstructural stability at these temperatures.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Physics, Fluids & Plasmas
L. W. Packer, P. Batistoni, N. Bekris, S. C. Bradnam, M. Fabbri, Z. Ghani, M. R. Gilbert, R. Kierepko, E. Laszynska, D. Leichtle, I. Lengar, S. Loreti, J. W. Mietelski, C. R. Nobs, M. Pillon, M. I. Savva, I. E. Stamatelatos, T. Vasilopoulou, A. Wojcik-Gargula, A. Zohar
Summary: The latest results from experimental activities conducted within the 'ACT' sub-project under the EUROfusion WPJET3 programme on irradiating ITER materials are presented, including analyses of various material samples and characterization of irradiation locations. These results also include comparisons with neutron transport and activation calculation predictions for the ITER samples.
Article
Physics, Fluids & Plasmas
Luca Reali, Max Boleininger, Mark R. Gilbert, Sergei L. Dudarev
Summary: In this study, we propose a method for computing macroscopic elastic stress and strain in components of a fusion power plant using the eigenstrain produced by defects in a material exposed to high energy neutron irradiation. Analytical and numerical analysis of several case studies related to the design of a fusion power plant show that the spatial distribution of defects leads to significant elastic stresses in ion-irradiated thin films, pressurized cylindrical tubes, and breeding blanket modules.
Article
Nuclear Science & Technology
A. Wojcik-Gargula, M. Rubel, P. Batistoni, N. Bekris, B. Colling, E. Dutkiewicz, T. Laas, C. R. Nobs, J. Paju, L. W. Packer, M. Perzanowski, P. Petersson, J. Priimets, T. Vasilopoulou
Summary: Titanium activation foils exposed in the JET tokamak vessel during an experimental campaign showed different degrees of degradation, with some foils only slightly affected while others completely disintegrated into dust or flakes. The presence of defects formed during sample preparation was found to be the cause of the degradation of the titanium crystal structure upon exposure to neutral particles, including hydrogen.
FUSION ENGINEERING AND DESIGN
(2022)
Article
Physics, Fluids & Plasmas
Sehila M. Gonzalez de Vicente, Nicholas A. Smith, Laila El-Guebaly, Sergio Ciattaglia, Luigi Di Pace, Mark Gilbert, Robert Mandoki, Sandrine Rosanvallon, Youji Someya, Kenji Tobita, David Torcy
Summary: In the absence of official standards and guidelines, fusion designers have adopted well-established standards for fission-based nuclear power plants. However, this approach may result in overconservative measures and increased cost and complexity. One important issue in fusion power is the generation of radioactive waste, which is significantly different from fission NPP waste. Fusion waste mainly consists of low-level and intermediate level waste, but without many long-lived isotopes. The use of reduced-activation materials in fusion technology allows for lower decay heat removal and rapid radioactivity decay.
Review
Energy & Fuels
Arunodaya Bhattacharya, Steven J. Zinkle, Jean Henry, Samara M. Levine, Philip D. Edmondson, Mark R. Gilbert, Hiroyasu Tanigawa, Charles E. Kessel
Summary: RAFM and ODS steels are the most promising candidates for fusion first-wall/blanket structures, but their performance will deteriorate due to neutron damage and gas effects during operation. Future development should target materials with lower chromium concentration to minimize irradiation-induced effects.
JOURNAL OF PHYSICS-ENERGY
(2022)
Article
Materials Science, Multidisciplinary
Shu Huang, Ryan Kerr, Samuel Murphy, Mark R. Gilbert, Jaime Marian
Summary: A numerical model is presented to predict oxide scale growth on tungsten surfaces under exposure to oxygen at high temperatures, with simulations showing deviations from classical parabolic growth in certain cases. The model is parameterized using experimental measurements and electronic structure calculations, with a comparison to extensive experimental data showing reasonable agreement at most temperatures. This work attempts to embed the thermodynamic and kinetic complexity of tungsten oxide growth into a comprehensive mesoscale kinetic model to fill existing knowledge gaps and guide future tungsten oxidation models.
MODELLING AND SIMULATION IN MATERIALS SCIENCE AND ENGINEERING
(2022)
Article
Nuclear Science & Technology
Sophia O. von Tiedemann, David M. Collins, Mark R. Gilbert, Ivan A. Kodeli
Summary: Predictions of material activity in commercial fusion conditions mostly rely on computational methods due to lack of data on long-term effects of high-energy neutron irradiation on structural steels. This study focused on modelling neutron activation of four structural steels in a fusion reactor environment after 20 years of operation. Eurofer and F82H steels exhibited higher resistance to neutron activation than G91 and SS316L(N)-IG. The vacuum vessel (SS316L(N)-IG) would not be classified as low-level waste for several centuries.
FUSION ENGINEERING AND DESIGN
(2023)
Article
Energy & Fuels
Mark R. Gilbert
Summary: Nuclear data is crucial for fusion experiments and future fusion power plants, as it provides information on neutron reaction probabilities and decay behavior. Inventory codes that use this data to predict the effects on materials are also important for managing radiological hazards and determining component lifetimes. Validated and accurate nuclear data and inventory codes are essential for the safe and efficient operation of fusion reactors.
JOURNAL OF PHYSICS-ENERGY
(2023)
Article
Materials Science, Multidisciplinary
Yichen Qian, Mark R. Gilbert, Lucile Dezerald, Duc Nguyen-Manh, David Cereceda
JOURNAL OF NUCLEAR MATERIALS
(2023)