Article
Nuclear Science & Technology
M. D'Onorio, D. N. Dongiovanni, I Ricapito, J. Vallory, M. T. Porfiri, T. Pinna, G. Caruso
Summary: The Water-Cooled Lithium Lead Breeding Blanket is a promising concept for fusion power devices, which requires testing before integration into a DEMO plant. A Test Blanket System is currently being designed for integration into ITER, with a focus on safety performance and accident analysis. Preliminary safety studies have been conducted to support the design and integration of the system, investigating the impact of different parameters on accident evolution and consequences.
FUSION ENGINEERING AND DESIGN
(2021)
Article
Nuclear Science & Technology
Seungyon Cho, Mu-Young Ahn, Young-Bum Chun, Hyoseong Gwon, Hyung Gon Jin, Bum Seok Kim, Chang-Shuk Kim, Jong-Il Kim, Suk-Kwon Kim, Duck Young Ku, Cheol Woo Lee, Dong Won Lee, Eo Hwak Lee, Hyeong-Yeon Lee, Youngmin Lee, Seong Dae Park, Soon Chang Park, Yi-Hyun Park, Chang Wook Shin, Seok-Kwon Son, Jae Sung Yoon, Sunghwan Yun
Summary: Development of the Helium Cooled Ceramic Reflector (HCCR) breeding blanket in Korea is focused on validating integrated design tools and core technologies, with a unique graphite reflector concept to reduce costs. The main functions and design concepts of HCCR breeding blanket will be verified in ITER, along with testing cooling, coolant purification, tritium extraction technologies before employed in DEMO.
FUSION ENGINEERING AND DESIGN
(2021)
Article
Construction & Building Technology
Ying Chen, Jingsi Huo, Hong Hao, Xiaoqing Zhou, Wensu Chen
Summary: This study investigates the behavior of butt welds and fillet welds under dynamic loads and analyzes the influence of weld strength matching on their performance. The results show that the strength of the welds increases with increasing strain rate, while the fracture strain decreases.
JOURNAL OF CONSTRUCTIONAL STEEL RESEARCH
(2023)
Article
Nuclear Science & Technology
C. Koehly, L. Buehler, C. Courtessole
Summary: The current reference concept for a European liquid metal test blanket module (TBM) for ITER is a water-cooled lead lithium (WCLL) blanket. The spatial distribution of cooling pipes in the blanket structure and breeding zone is a critical issue, as efficient heat removal from the liquid metal needs to be ensured. The design of the manifolds, which have complex geometrical structures, has a significant impact on the flow partitioning in the blanket.
FUSION ENGINEERING AND DESIGN
(2023)
Article
Nuclear Science & Technology
Jun -sung Chang, Sa-woong Kim, Si-kun Chung, Kwan-woo Nam, Duck-Hoi Kim, Hyun-Soo Kim, Hyeon-Gon Lee, Ki-Jung Jung
Summary: The ITER Blanket Shield Block (SB) is a key in-vessel component responsible for nuclear shielding and heat removal in the ITER project. To ensure the integrity of welded joints and prevent leakage during manufacturing and testing, two Hot Helium Leak Test (HHLT) facilities have been constructed and commissioned by the ITER Korea Domestic Agency (KODA). This paper presents the design features and lessons learned from the HHLT facilities.
FUSION ENGINEERING AND DESIGN
(2023)
Article
Biotechnology & Applied Microbiology
Yuanyuan Chen, Haitao Li, Xiao Sun
Summary: This study utilized the 2-order network theory and hub-gene theory to construct sample-specific driver modules, identifying individual perturbation networks driven by mutations or methylation aberrations. The research revealed common driver patterns and subtype-specific driver modules in breast cancer, reflecting survival prognosis and malignancy degree. The findings contribute to a better understanding of breast cancer mechanisms driven by mutations and methylation variations, potentially leading to new therapeutic combinations.
Article
Nuclear Science & Technology
Stephane Gazzotti, Vincent Weistroffer, Killian Huc, Christine Megard, Chiara Di Paolo, Paul Viudes, Fabien Ferlay, Claude Andriot, Jean-Pierre Friconneau, Jean-Pierre Martins
Summary: This article introduces a mixed (digital & physical) validation approach with immersive technology to verify the feasibility of Test Blanket Modules (TBM) replacement operations in ITER Port Cells. The main validation criteria include operator accessibility, posture, procedure sequence, and time spent at workstations. Virtual reality tools have proven to be effective in developing credible replacement scenarios and optimizing the process to minimize radiation exposure.
FUSION ENGINEERING AND DESIGN
(2023)
Article
Engineering, Electrical & Electronic
Zhang Ying, Yushan Zhao, Erping Deng, Maoyang Pan, Luhong Xie, Yongzhang Huang
Summary: In this article, an advanced power cycling method for power modules with low thermal resistance is proposed, which allows them to perform power cycling tests (PCT) at rated current without changing lifetime and failure modes. By analyzing the influencing factors of parameters in the PCT, a new method is proposed to affect the parameters of the power cycle by changing the external thermal resistance. The influence of different external thermal resistances on PCT parameters and failure modes is also analyzed.
IEEE JOURNAL OF EMERGING AND SELECTED TOPICS IN POWER ELECTRONICS
(2023)
Article
Energy & Fuels
Birinchi Bora, Supriya Rai, Arup Dhar, Chandan Banerjee
Summary: This study analyzed the degradation of 20-year field-operated PV modules, finding that it is mainly caused by the combined effect of environmental conditions and UV irradiation. After 20 years of exposure, the average deterioration rates for Pmax, Isc, and Voc were 1.49%/year, 0.59%/year, and 0.29%/year, respectively. The study also analyzed the effects of UV irradiation and temperature in indoor conditions, as well as module browning.
Article
Nuclear Science & Technology
T. Zaouter, K. Vulliez, B. Michel, S. Gazzotti, J-P Friconneau, J-P Martins
Summary: The TBM program in ITER aims to validate concepts for the DEMO tritium Breeding Blankets, requiring the PF pipe forest to withstand severe thermomechanical loads during plasma operation while providing protection and ease of operation. This study assesses the use of bolted flanges as an alternative to welded solutions for connecting the PF on the TBMs inside the port cell environment, showing that bolted-flange junctions are a credible solution despite the presence of important stresses in the flange socket.
FUSION ENGINEERING AND DESIGN
(2021)
Article
Engineering, Mechanical
Stefanos Gkatzogiannis, Joscha Weinert, Imke Engelhardt, Peter Knoedel, Thomas Ummenhofer
Summary: The study investigates the corrosion fatigue behavior of structural steel weldments treated with HFMI. Laboratory simulation of marine corrosion, along with fatigue testing, reveals that HFMI treatment significantly improves the corrosion fatigue resistance of weldments. Recommendations for future research are also discussed.
INTERNATIONAL JOURNAL OF FATIGUE
(2021)
Article
Energy & Fuels
Hyungjin Son, Hyunsoo Lim, Jiyeon Moon, Dayoung Jun, Byeong-Kwon Ju, Sunghyun Kim
Summary: This study investigates the environmental stability of an electrically conductive adhesive (ECA) used in shingled photovoltaic (PV) modules. The results show that the electrical properties of the ECA did not deteriorate under hot and humid conditions, but the performance of the shingled modules degraded due to current leakage causing a drop in the fill factor (FF). Physicochemical analysis revealed that silver atoms diffused from the ECA joint to the silicon wafer, acting as a shunt path for the solar cell.
SOLAR ENERGY MATERIALS AND SOLAR CELLS
(2022)
Article
Engineering, Multidisciplinary
Hailiang Nie, Weifeng Ma, Kai Xue, Junjie Ren, Wei Dang, Ke Wang, Jun Cao, Tian Yao, Xiaobin Liang
Summary: This paper proposes a specimen processing method for weld characteristic zones and solves the issue of lack of weld mechanical properties in existing steel pipe safety evaluations. Testing an X80 automatic girth weld showed significant differences in tensile properties between different characteristic zones, highlighting the need for a more detailed assessment of weld properties in practical engineering and safety evaluations.
INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING
(2021)
Article
Medicine, Research & Experimental
Jinting Guan, Yiping Lin, Yang Wang, Junchao Gao, Guoli Ji
Summary: Identifying cell type-specific disease gene modules can provide new insights into the pathogenesis and progression of diseases, leading to the development of more targeted treatments and biomarkers. The study also highlights the importance of studying different disorders and their similarities and differences at the molecular level to better understand the underlying mechanisms of diseases.
JOURNAL OF TRANSLATIONAL MEDICINE
(2021)
Article
Energy & Fuels
Depeng Li, Wei Liu, Xiaoshuang Li, Haijun Tang, Guichun Xu, Deyi Jiang, Jinwu Du, Xiong Zhang, Jinyang Fan
Summary: This study conducted experimental and theoretical research on the physical simulation of salt cavern construction with light brine under gas blanket. The results show that using light brine and gas blanket can reduce costs and improve environmental protection. This research provides a basis for promoting clean and efficient brine mining and salt cavern energy storage.
JOURNAL OF ENERGY STORAGE
(2022)
Article
Materials Science, Multidisciplinary
Pavel V. Vladimirov, Vladimir P. Chakin, Michael Duerrschnabel, Ramil Gaisin, Aniceto Goraieb, Francisco Alberto Hernandez Gonzalez, Michael Klimenkov, Michael Rieth, Rolf Rolli, Nikolai Zimber, Sergey Udartsev, Maxim Kolmakov, Anatoly Vechkutov, Evgeniy Frants
Summary: Neutron multiplier materials are crucial for tritium production and fuel cycle closure in fusion reactors. The traditional pebble bed concept faces challenges such as tritium accumulation and safety issues, leading to the exploration of advanced materials like beryllides. The transition to beryllides allows for a shift from the pebble bed concept to a solid hexagonal block-based one, addressing issues of tritium retention and safety concerns.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
Shuhei Nogami, Akira Hasegawa, Makoto Fukuda, Michael Rieth, Jens Reiser, Gerald Pintsuk
Summary: This paper discusses the drawbacks of tungsten as a plasma facing material in fusion reactors and the efforts to improve its mechanical properties through collaborative research and development. Methods such as grain refining, K-doping, dispersion strengthening, and alloying with Re are explored to enhance the performance of tungsten materials. However, there are concerns regarding the intrinsic issues of materials alloyed with Re under high dose neutron irradiation.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
M. Richardson, M. Gorley, Y. Wang, G. Aiello, G. Pintsuk, E. Gaganidze, M. Richou, J. Henry, R. Vila, M. Rieth
Summary: A dedicated procedure was developed to categorize the technology readiness of materials for specific DEMO in-vessel fusion reactor applications. The study highlights the challenges facing DEMO materials development and the introduction of a biennial review to facilitate more effective planning and targeted materials development within WPMAT.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
Philipp Lied, Wolfgang Pantleon, Carsten Bonnekoh, Simon Bonk, Andreas Hoffmann, Jens Reiser, Michael Rieth
Summary: The addition of potassium-doping in tungsten sheets has been found to improve mechanical properties, especially with a lower brittle-to-ductile transition temperature in cold-rolled sheets, attributed to finer grain size. This suggests the potential for increased performance in high-temperature environments compared to pure tungsten.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
M. Duerrschnabel, E. Gaisina, R. Gaisin, M. Walter, J. Aktaa, M. Rieth
Summary: This study provides a detailed nanoscale insight into the corrosion of EUROFER steel by Li-based ceramics using analytical electron microscopy (AEM) analyses. A bilayer corrosion zone was observed, with structurally disordered LiFeO2 and ferrite in the outer zone, and complex spinel-type oxides in the inner zone. Additionally, it was found that M23C6 precipitates in EUROFER steel were dissolved, while MX-type transition metal nitrides were not. Suggestions to minimize the corrosion issue were also provided.
Article
Nuclear Science & Technology
Gerald Pintsuk, Giaocomo Aiello, Sergei L. Dudarev, Michael Gorley, Jean Henry, Marianne Richou, Michael Rieth, D. Terentyev, Rafael Vila
Summary: The EUROfusion materials research program focuses on developing materials for in-vessel components of the DEMO fusion reactor, aligning with the European Fusion Roadmap. It includes characterization and qualification of baseline materials, advanced materials for risk mitigation, and functional materials. The program aims to provide qualified data to support the engineering design activities and generate necessary reports and handbooks.
FUSION ENGINEERING AND DESIGN
(2022)
Article
Nuclear Science & Technology
Arunodaya Bhattacharya, Xiang Chen, Tim Graening, Josina W. Geringer, Jordan Reed, Jean Henry, Luciano Pilloni, Dmitry Terentyev, Athina Puype, Thak Sang Byun, Yutai Katoh, Michael Rieth, Steven J. Zinkle
Summary: Ten Eurofer97 steel variants were irradiated in a high flux isotope reactor under ITER-TBM relevant conditions for mechanical property tests. The study showed all steels suffered from irradiation hardening with varying levels, leading to a significant increase in yield stress and loss of elongation. Despite significant hardening and reduced elongation, most failures were ductile, but post-necking ductility varied between materials. After irradiation, the ultimate tensile stress to yield stress ratios decreased significantly, indicating strain hardening capacity reduction. No major effect on plastic instability stress and true fracture stress was observed. Work hardening capability after irradiation should be a target for RAFM steel designing. The tensile data revealed an inverse trend between reduced elongation and increased yield stress of neutron irradiated Eurofer97 steels.
FUSION ENGINEERING AND DESIGN
(2021)
Article
Nuclear Science & Technology
Simon Bonk, Michael Duerrschnabel, Heiko Neuberger, Esther Simondon, Michael Rieth
Summary: Additive manufacturing of EUROFER97 components requires post-processing steps such as heat treatment to achieve a uniform martensitic microstructure similar to conventionally produced EUROFER97, including the formation of M23C6 and MX precipitates.
FUSION ENGINEERING AND DESIGN
(2021)
Article
Materials Science, Multidisciplinary
P. Fernandez, J. Hoffmann, M. Rieth, A. Gomez-Herrero
Summary: The composition of new 8%Cr reduced activation ferritic/martensitic steels have been finely tuned to increase fine MX precipitates and reduce coarse M23C6 carbides through thermomechanical treatments. The study shows that higher nitrogen content favors M2X precipitation over MX, with vanadium contents around 0.2 wt%. MX-Ti rich precipitates are larger in size than MX (Ta or V rich). EELS analysis indicates that the precipitates of MX (Ta, V and Ti rich) after tempering at 750 degrees C/2 h are mainly carbo-nitrides. Discussions are held on the composition, size, number density, carbon, and nitrogen content of MX and M2X in relation to each alloy.
MATERIALS CHARACTERIZATION
(2021)
Article
Physics, Fluids & Plasmas
D. Terentyev, M. Rieth, G. Pintsuk, J. Riesch, A. von Mueller, S. Antusch, K. Mergia, E. Gaganidze, H. -C. Schneider, M. Wirtz, S. Nogami, J. Coenen, J. H. You, A. Zinovev, W. Van Renterghem
Summary: This contribution presents the results of recent irradiation campaigns on advanced tungsten and copper-based materials, which are main candidates for use in plasma-facing components. The challenges of the irradiation programme include evaluating the ductile-to-brittle transition temperature of newly developed tungsten-based materials, investigating the performance of industrial pure tungsten grade under high temperature irradiation, and assessing the high temperature strength of CuCrZr-based alloys and composites.
Article
Chemistry, Multidisciplinary
Michael Rieth, Michael Duerrschnabel, Simon Bonk, Ute Jaentsch, Thomas Bergfeldt, Jan Hoffmann, Steffen Antusch, Esther Simondon, Michael Klimenkov, Carsten Bonnekoh, Bradut-Eugen Ghidersa, Heiko Neuberger, J. Rey, Christian Zeile, Gerald Pintsuk, Giacomo Aiello
Summary: Plasma facing components for future nuclear fusion reactors require a variety of fabrication processes, which have different effects on the properties of steel. Research has shown that robust fabrication routes can meet industrial demands, with successful application in first-wall mock-up fabrication. High heat flux testing indicates the viability of using available industrial processes to fabricate future breeding blankets.
APPLIED SCIENCES-BASEL
(2021)
Article
Nuclear Science & Technology
Aleksandr Zinovev, Dmitry Terentyev, Chih-Cheng Chang, Chao Yin, Alexander Bakaev, Michael Rieth, Philipp Lied, Jens Reiser, Carsten Bonnekoh
Summary: This study investigates the behavior of tungsten foils and bulk tungsten under neutron irradiation. The irradiated tungsten foils retain their ductility at room temperature and show no significant irradiation hardening or DBTT shift compared to bulk tungsten. The different effects of irradiation embrittlement may be attributed to the irradiation-assisted diffusion of copper solutes in the tungsten foils.
NUCLEAR MATERIALS AND ENERGY
(2022)
Article
Materials Science, Multidisciplinary
Shuhei Nogami, Itsuki Ozawa, Daisuke Asami, Naoya Matsuta, Seiji Nakabayashi, Siegfried Baumgaertner, Philipp Lied, Kiyohiro Yabuuchi, Takeshi Miyazawa, Yuta Kikuchi, Marius Wirtz, Michael Rieth, Akira Hasegawa
Summary: The addition of tantalum to tungsten-tantalum alloys improves their mechanical properties, resistance against recrystallization, and resistance to high heat flux exposure. This makes them a promising material for fusion reactor applications.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Materials Science, Multidisciplinary
M. Klimenkov, M. Duerrschnabel, U. Jaentsch, P. Lied, M. Rieth, H. C. Schneider, D. Terentyev, W. Van Renterghem
Summary: Pure W material was neutron irradiated at temperatures ranging from 600°C to 1200°C, resulting in the formation of voids, dislocation loops, and W-Re-Os containing precipitates. The microstructure analysis revealed the detailed structure of these defects, including the size and distribution of voids, precipitates, and loops. Additionally, chemical and structural analysis showed that the defects were surrounded by a solid solution cloud enriched with Re and Os, and nanoscale chemical analysis identified differences in Re/Os segregation at and near the defects.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Proceedings Paper
Energy & Fuels
Alexandru Onea, Wolfgang Hering, Sven Ulrich, Michael Rieth, Alfons Weisenburger, Jens Reiser, Stephan Lenk, Thomas Roebert, Steffen Vielhaber, Siegfried Baumgaertner, Rainer Ziegler, Robert Stieglitz
Summary: This paper describes the development of a 1000K sodium loop at the Karlsruhe Institute of Technology for investigating the creep fatigue and corrosion/erosion of new materials in concentrating solar power plants. The construction of the high temperature loop is motivated by the lack of experimental data for steels in flowing sodium above -650°C. The study discusses the loop operation procedures, safety measures, and presents some experimental results and new materials proposed for the receiver.
SOLARPACES 2020 - 26TH INTERNATIONAL CONFERENCE ON CONCENTRATING SOLAR POWER AND CHEMICAL ENERGY SYSTEMS
(2022)
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)
