Article
Materials Science, Ceramics
Dong Zhao, Andre Broussard, Tiankai Yao, Kevin Yan, Heng Ban, Jie Lian
Summary: This paper presents an innovative approach using spark plasma sintering (SPS) combined with finite element modeling (FEM) to study the transient behavior of nuclear fuels. The temperature ramping rates of SPS can simulate the thermal profiles of loss-of-coolant-accident (LOCA) and reactivity-induced-accident (RIA) events. Experimental results show that micron-sized fresh UO2 pellets synthesized by SPS exhibit good thermal shock stability and anti-cracking performance under LOCA thermal testing, while cracking occurs under simulated RIA conditions due to the stress induced by large thermal gradients. The unique capability of SPS with controlled temperature ramping enables a cost-effective method for rapid screening and evaluation of nuclear fuels under power transients.
JOURNAL OF THE EUROPEAN CERAMIC SOCIETY
(2024)
Article
Materials Science, Multidisciplinary
G. Pastore, K. A. Gamble, R. L. Williamson, S. R. Novascone, R. J. Gardner, J. D. Hales
Summary: The study discusses the developments and validation of the BISON fuel performance code for Zircaloy cladding behavior and UO2 fuel behavior during LOCA conditions. The results show that the code can effectively simulate the pressure evolution and cladding burst time of fuel rods during LOCA transients, but the selection of burst failure criterion is considerably sensitive, making it difficult to accurately evaluate cladding strains during postulated LOCA scenarios.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
G. Pastore, R. L. Williamson, R. J. Gardner, S. R. Novascone, J. B. Tompkins, K. A. Gamble, J. D. Hales
Summary: This paper presents the BISON modeling developments and validation of Zircaloy nuclear fuel cladding behavior under LOCA conditions. The validation calculations show good agreement with experimental data.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
K. Kane, S. Bell, B. Garrison, M. Ridley, M. Gussev, K. Linton, N. Capps
Summary: Extensive testing is required to develop and verify nuclear fuel-cladding performance codes. This study presents a technique to experimentally quantify the relationship between temperature, cladding internal pressure, and strain during a burst test. The results show good agreement between measured and simulated strains, with potential for model improvement in the moments leading up to burst.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Thermodynamics
Shuichiro Miwa, Takashi Hibiki
Summary: Understanding the inverted annular flow (IAF) boiling regime is crucial for various engineering disciplines. The IAF is a post-dryout, or post-CHF film boiling regime in forced convective flow in tubes or channels. The flow regime transitions and heat transfer correlations of IAF are important for the safety analysis of modern nuclear reactors.
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER
(2022)
Article
Nuclear Science & Technology
Chaoqun Deng, Yanan He, Fengrui Xiang, Yingwei Wu, Jing Zhang, Wenxi Tian, Guanghui Su, Suizheng Qiu
Summary: This study investigates the thermomechanical behaviors of U3Si2-FeCrAl system as a potential accident tolerant fuel candidate. By simulating CABRI-REP tests and comparing with other systems, it is found that U3Si2-FeCrAl system can increase fuel temperature and delay gap closure during normal operation, but poses a threat to fuel central temperature under RIA conditions.
PROGRESS IN NUCLEAR ENERGY
(2022)
Article
Nuclear Science & Technology
Rohit Kumar, Manish Mishra, Onkar Gokhale, D. Mukhopadhyay
Summary: The study investigates the thermal behavior, steam ingression, and hydrogen generation of pressurized heavy water reactors in severe accidents. Experimental and numerical analysis showed that the fuel bundle in the channel reaches a maximum temperature of 891 degrees C, with an average hydrogen generation rate of 0.01822 g/s. Steam ingression causes oxidation near the end of the channels, but radiation and convective steam cooling help to limit temperature rise.
NUCLEAR ENGINEERING AND DESIGN
(2021)
Article
Nuclear Science & Technology
Yinbin Miao, Aaron Oaks, Kun Mo, Michael Billone, Christopher Matthews, Adam X. Zabriskie, Stephen Novascone, Abdellatif M. Yacout
Summary: The report highlights the development and implementation of BISON's FCCI/CCCI correlations and cladding degradation models, demonstrating their improved predictive capabilities and identifying limitations that will be addressed through BISON-FIPD integration efforts.
NUCLEAR ENGINEERING AND DESIGN
(2021)
Article
Nuclear Science & Technology
Shengyu Liu, Rong Liu, Chenjie Qiu
Summary: This study introduces the concept of internal and external cooled annular fuel, develops corresponding codes and multiphysics models, and compares the performance of annular fuel with solid fuel under different conditions. It is found that annular fuel has advantages in reducing maximum temperature and fuel melting risk.
PROGRESS IN NUCLEAR ENERGY
(2022)
Article
Materials Science, Multidisciplinary
Jason D. Hales, Wen Jiang, Aysenur Toptan, Kyle A. Gamble
Summary: This paper discusses the simulation of fission product diffusion in TRISO fuel particles using the finite element method with the fuel performance code BISON. Recent material model development has been done in BISON for each material present in TRISO fuel particles, and a significant validation effort showed that BISON outputs compare favorably to experimental data and other software tools.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Nuclear Science & Technology
Muhammet Enis Kanik, Omid Noori-kalkhoran, Kevin Fernandez-Cosials, Massimiliano Gei
Summary: This study analyzes the short-term thermal-hydraulic parameters of a VVER-1000/V446 reactor containment during a postulated severe accident. Through three-dimensional modeling and simulation, detailed parameters of the containment at various coordinates over time are obtained. These results are important for the precise positioning and installation of safety features in design and operation.
PROGRESS IN NUCLEAR ENERGY
(2022)
Article
Nuclear Science & Technology
Yinbin Miao, Aaron Oaks, Kun Mo, Shipeng Shu, Nicholas Fassino, Christopher Matthews, Stephen Novascone, Abdellatif M. Yacout
Summary: This study presents a framework for evaluating the swelling model of low-burnup SFR metallic fuel using BISON. The framework utilizes experimental data from the Integral Fast Reactor program and enables standardized and automated use of legacy metallic fuel irradiation data.
NUCLEAR ENGINEERING AND DESIGN
(2023)
Article
Materials Science, Multidisciplinary
K. A. Kane, P. I. M. Stack, P. A. Mouche, R. R. Pillai, B. A. Pint
Summary: In this study, Cr coatings were deposited on SiC and the reaction products and mass changes at high temperatures were investigated. The results show that the Cr coatings did not have a detrimental impact on the steam oxidation resistance of SiC.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Veterinary Sciences
Alexandra Corduneanu, Marian Taulescu, Teodor Dan Ursache, Angela Monica Ionica, Andrei Daniel Mihalca
Summary: The aim of this study was to evaluate the presence of apicomplexan parasites in blood and tissues of farmed American bison from Romania. A total of 222 blood samples and 11 tissue samples were tested using PCR, and the overall prevalence of piroplasmid infection was found to be 1.65%, with Babesia divergens and Theileria sp. identified following sequencing. This is the first report of piroplasms detected in blood and tissues of farmed B. bison from Europe, highlighting the need for further studies to understand the epidemiological status and clinical relevance of piroplasms in farmed American bisons.
FRONTIERS IN VETERINARY SCIENCE
(2023)
Article
Nuclear Science & Technology
Andre Luiz Pereira Rebello Jr, Harish C. Huria, Aquilino Senra Martinez, Alessandro da Cruz Goncalves
Summary: The neutronic characteristics of the annular fuel were analyzed using the PARAGON2 code and compared with the MCNP code. The Ultra-Fine Energy Mesh Library was used to eliminate resonance self-shielding calculation.
ANNALS OF NUCLEAR ENERGY
(2023)
Article
Nuclear Science & Technology
Yandong Hou, Liu Wang, Mingjun Wang, Kui Zhang, Xisi Zhang, Wenjun Hu, Yingwei Wu, Wenxi Tian, Suizheng Qiu, G. H. Su
PROGRESS IN NUCLEAR ENERGY
(2020)
Article
Energy & Fuels
Wei Li, Koroush Shirvan, Shay Harrison, Joseph Pegna
Article
Chemistry, Physical
Arunkumar Seshadri, Eric C. Forrest, Koroush Shirvan
APPLIED SURFACE SCIENCE
(2020)
Article
Physics, Fluids & Plasmas
R. Patrick White, Koroush Shirvan
IEEE TRANSACTIONS ON PLASMA SCIENCE
(2020)
Article
Materials Science, Multidisciplinary
Michael W. D. Cooper, Giovanni Pastore, Yifeng Che, Christopher Matthews, Axel Forslund, Christopher R. Stanek, Koroush Shirvan, Terje Tverberg, Kyle A. Gamble, Brian Mays, David A. Andersson
Summary: The study focuses on the enhanced fission gas diffusivity in Cr2O3-doped UO2 pellets, showing that doping results in increased uranium and oxygen vacancies, leading to improved fission gas release suppression. The new physics-informed model was validated against in-reactor experimental measurements and demonstrated noticeable improvements over the standard UO2 behavior in fission gas release.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Nuclear Science & Technology
Yue Jin, Fan-Bill Cheung, Koroush Shirvan, Stephen M. Bajorek, Kirk Tien, Chris L. Hoxie
ANNALS OF NUCLEAR ENERGY
(2020)
Article
Materials Science, Multidisciplinary
Ekaterina Ryabikovskaya, Aaron French, Adam Gabriel, Hyosim Kim, Tianyao Wang, Koroush Shirvan, Frank A. Garner, Lin Shao
Summary: Pure chromium was irradiated with Fe ions at different temperatures and peak dpa levels, showing varying swelling behavior. However, the swelling rate was found to be relatively low, insensitive to dpa rate, and with an incubation period. Self-organization in the form of void ordering was observed, with the void alignment direction determined to be the (111) axial direction.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
J. Hazan, A. Gauthier, E. Pouillier, K. Shirvan
Summary: Research has shown that cold-spray chromium coated zircaloy claddings can reduce ballooning and burst while increasing burst temperature in high temperature conditions. However, these tests demonstrate limited benefits in post-quench behavior of coated specimens in the last stage of a prototypical LOCA scenario.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Nuclear Science & Technology
Majdi Radaideh, Isaac Wolverton, Joshua Joseph, James J. Tusar, Uuganbayar Otgonbaatar, Nicholas Roy, Benoit Forget, Koroush Shirvan
Summary: The study explores the effectiveness of reinforcement learning algorithms in optimizing nuclear fuel assemblies. By embedding expert knowledge and effectively exploring the search space, RL outperforms stochastic optimization algorithms in solving high-dimensional problems. This method demonstrates RL's potential as a decision support tool for nuclear fuel assembly optimization, providing more feasible patterns and increased search speed.
NUCLEAR ENGINEERING AND DESIGN
(2021)
Article
Materials Science, Multidisciplinary
Arunkumar Seshadri, Bren Philips, Akshay J. Dave, Shay Harrison, Joseph Pegna, Koroush Shirvan
Summary: This study introduces the microstructure and mechanical properties of SiC fibers prepared by Laser Chemical Vapor Deposition (LCVD), compares the hydrothermal corrosion of different stoichiometric SiC fibers, and concludes that the dissolution of the SiC fibers under radiation and high-temperature, high-pressure conditions depends on factors such as stoichiometric ratio.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Computer Science, Artificial Intelligence
Majdi Radaideh, Koroush Shirvan
Summary: In this study, a rule-based RL method is proposed to guide evolutionary algorithms in constrained optimization, showing significant improvement in continuous optimization over standalone algorithms. RL-guided EA outperforms standalone algorithms by more than 10 times in exploration capabilities and computational efficiency, indicating the effectiveness of RL in focusing the search space in areas where expert knowledge has merit.
KNOWLEDGE-BASED SYSTEMS
(2021)
Article
Green & Sustainable Science & Technology
W. R. Stewart, K. Shirvan
Summary: The FOAK nuclear plants built in the last 20 years have experienced budget and schedule overruns. The small modular reactor (SMR) is proposed as a remedy, showcasing economic competitiveness through multiple units, increased factory production, reduced construction schedules, plant design simplification, and unit timing. A bottom-up study comparing near-term light water reactor SMRs with Gen III+ large plants has not been conducted. This work presents a cost estimating methodology using a detailed bottom-up approach for over 200 structures, systems, and components of nuclear plants.
RENEWABLE & SUSTAINABLE ENERGY REVIEWS
(2022)
Article
Nuclear Science & Technology
Yeongshin Jeong, Koroush Shirvan, Michael Buric
Summary: This work establishes a generic multiphysics tool for liquid-fueled molten salt reactors (LFMSRs) and applies it to a reference design. It investigates the dynamic and thermal responses of the reactor during operational transients and suggests the use of continuous temperature monitoring with fiber optics to improve safety.
NUCLEAR SCIENCE AND ENGINEERING
(2023)
Article
Materials Science, Multidisciplinary
Arunkumar Seshadri, Koroush Shirvan
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Nuclear Science & Technology
W. Robb Stewart, Koroush Shirvan
Summary: Capital cost and construction schedule estimates for nuclear projects often underestimate realized costs upon project completion. This paper explores the risk of different construction delay drivers and their impact on total installed cost for various reactor architectures. The study shows significant risk of cost overrun and schedule delays, with multi-module plants being the most susceptible to construction delays and small modular BWRs being the least susceptible. Design changes and productivity hits are identified as the primary drivers of construction delays.
NUCLEAR ENGINEERING AND DESIGN
(2023)
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)