Article
Materials Science, Multidisciplinary
Patrik Sahiluoma, Yuriy Yagodzinskyy, Sven Bossyut, Hannu Haenninen
Summary: Spent nuclear fuel is planned to be stored in thick copper canisters at a considerable depth in the bedrock. However, hydrogen uptake in the copper can occur due to corrosion and irradiation effects. Understanding the conditions that lead to the formation of pressurized hydrogen bubbles near the copper surface is crucial. Experimental measurements showed that hydrogen bubbles grow and form voids near the copper surface, with plastic deformation and increasing temperature being contributing factors. The study also found a threshold potential for increased hydrogen uptake and void formation.
JOURNAL OF NUCLEAR MATERIALS
(2023)
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, Coatings & Films
Peter A. Mouche, Takaaki Koyanagi, Deep Patel, Yutai Katoh
Summary: Chromium deposited by high-power impulse magnetron sputtering (HiPIMS) and cathodic arc (CA) processes have different mechanical properties, but combining the two can create a single-phase coating with superior performance. By depositing an initial layer of Cr by HiPIMS followed by a layer of Cr by CA, a more adherent coating can be achieved, resolving some of the stress issues with CA morphology.
SURFACE & COATINGS TECHNOLOGY
(2021)
Article
Nuclear Science & Technology
M. Frankl, M. Wittel, N. Diomidis, A. Vasiliev, H. Ferroukhi, S. Pudollek
Summary: This article presents the technical foundation for a criticality safety assessment for the Swiss HLW deep geological repository concept and discusses the potential impact of ELB corrosion scenarios on the system's criticality.
ANNALS OF NUCLEAR ENERGY
(2023)
Article
Energy & Fuels
Laura Rodriguez-Penalonga, B. Yolanda Moratilla-Soria
Summary: The article presents two economic analyses conducted with the Marino model to analyze the costs of different spent nuclear fuel management strategies in the Spanish context. The analyses include a Monte Carlo study for strategies and the effects of longer operational lifetimes for Spanish nuclear power plants on management costs. The results show that longer operational lifetimes can compensate for extra costs caused by larger amounts of SNF, and a strategy without a centralized interim storage facility may be the most economically favorable.
INTERNATIONAL JOURNAL OF ENERGY RESEARCH
(2021)
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
Chemistry, Physical
Inesh Kenzhina, Petr Blynskiy, Artem Kozlovskiy, Meiram Begentayev, Saulet Askerbekov, Zhanna Zaurbekova, Aktolkyn Tolenova
Summary: The purpose of this study is to evaluate the morphological, structural, and strength properties of the new-generation TRISO fuel and examine their resistance to external influences. The research reveals that the samples have a high degree of resistance to external mechanical impacts and exhibit high resistance to high-dose irradiation in the near-surface layer.
Article
Green & Sustainable Science & Technology
Andrea Paulillo, Jonathan M. Dodds, Stephen J. Palethorpe, Paola Lettieri
Summary: The study assesses future scenarios for the back-end of the UK nuclear fuel cycle, considering direct disposal and four reprocessing scenarios. It highlights the importance of recycling uranium and plutonium, showing that reprocessing scenarios involving recycling of both materials are the most favorable options. The study also explores marginal technologies due to market uncertainty.
SUSTAINABLE MATERIALS AND TECHNOLOGIES
(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
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)
Review
Chemistry, Physical
Guanyu Jiang, Donghai Xu, Peng Feng, Shuwei Guo, Jianqiao Yang, Yanhui Li
Summary: This work provides a comprehensive review on the corrosion behavior of Zircaloy and FeCrAl alloys in nuclear reactors. FeCrAl cladding shows different kinetics in corrosive environments and may exhibit single, duplex or triple oxide layers. Developing challenges and prospects of FeCrAl alloys are discussed to expand its commercial scale in nuclear fuel cladding.
JOURNAL OF ALLOYS AND COMPOUNDS
(2021)
Article
Nuclear Science & Technology
Hongyang Wei, Jing Zhang, Xiaobin Jian, Yongdong Zhang, Lei Li, Shurong Ding, Qisen Ren
Summary: In this study, the effects of TRISO particle volume fraction, particle distribution pattern, and irradiation conditions on the thermal-mechanical behavior in FCM fuel pellets were investigated using the self-developed code TMAIMF. The results show that increasing the particle volume fraction leads to an increase in central temperature and a decrease in radial size increment, while the maximum tensile stresses of each coating layer of the TRISO particles vary slightly. The distribution pattern of the particles has a weak influence on temperature, deformation, and maximum tensile stress. The integrity of FCM pellets can be maintained under high fission rate conditions and extended burnup levels. The finite element models with axial displacement constrained are representative and yield more conservative analysis results compared to the free-end models. The numerical simulation results demonstrate the flexibility of optimizing TRISO-particle-based fuel pellets to meet the demands of economy and safety.
NUCLEAR MATERIALS AND ENERGY
(2023)
Article
Energy & Fuels
Marcus Seidl, Peter Schillebeeckx, Dimitri Rochman
Summary: The accuracy of predicting source term is crucial for efficient storage of spent nuclear fuel. Accurate codes are needed to predict decay heat and gamma and neutron sources over a wide time range. Currently, there is limited validation data and the uncertainty distribution in measurement-theory comparisons affects code validation efforts.
FRONTIERS IN ENERGY RESEARCH
(2023)
Article
Nuclear Science & Technology
Mika Kari, Matti Kojo, Markku Lehtonen
Summary: Finland and Sweden have advanced plans for final disposal of spent nuclear fuel and utilize a 'partnering' approach, but differ in key aspects of their nuclear waste policies, particularly in the role of communities in siting and licensing of repositories. Finland's approach is characterized by trust in safety authorities with community economics as the primary concern, while Sweden adopts an 'involved partnership' approach that challenges and modifies policies and actions.
PROGRESS IN NUCLEAR ENERGY
(2021)
Article
Materials Science, Multidisciplinary
Breanna K. Vestal, Jordan Travis, Austin Albert, Stephanie Bruffey, Joanna McFarlane, Emory D. Collins, Rodney D. Hunt, Craig E. Barnes
Summary: A potential new zirconium recycling protocol using unirradiated Zircaloy-based claddings and depleted uranium oxide has been demonstrated for the chemical removal of zirconium alloy cladding in used nuclear fuel rods. This involves a lower temperature chlorination reaction of zirconium with sulfur monochloride, separation of zirconium chloride using thionyl chloride, and purification by recrystallization from thionyl chloride. The protocol reduces technical complications and has been successfully tested on a small scale.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Nuclear Science & Technology
Orestes Castillo-Hernandez, P. E. Manuel Perdomo-Ojeda, C. R. Grantom, Pamela F. Nelson
Summary: Incorporating specified safety and production targets during the design phase can reduce costs and enhance the competitiveness of nuclear power plants. This paper presents two methods for proposing unavailability targets for nuclear reactor systems to optimize the design features. The methods are applied to a hypothetical facility, providing a basis for future work on estimating design alternatives affecting unavailabilities.
NUCLEAR ENGINEERING AND DESIGN
(2024)
Article
Nuclear Science & Technology
Qinjun Fu, Andre Bergeron, Philippe Fillion, Yohan Davit, Michel Quintard
Summary: In normal operating conditions, the flow within a pressurized water reactor (PWR) core primarily moves in the axial direction along the fuel rods. However, in accidents situations, transverse flows can have a significant impact on the thermal-hydraulic properties of the core. This study develops macroscopic pressure drop models for different flow directions and Reynolds numbers and validates them by comparing with existing system code results.
NUCLEAR ENGINEERING AND DESIGN
(2024)
Article
Nuclear Science & Technology
Xiang Chai, Xinyue Liu, Chaoran Guan, Tengfei Zhang, Xiaojing Liu
Summary: Micro nuclear reactors have gained attention for their high efficiency and long lifetime, making them suitable for remote and off-grid locations. This study examines the effects of burnable poisons on the performance of a micro nuclear reactor and improves the design for reactivity control. The computational results show that burnable poisons reduce excess reactivity and power peaking factor without significant impact on core lifetime.
NUCLEAR ENGINEERING AND DESIGN
(2024)
Article
Nuclear Science & Technology
Liwei Chen, Cong Zhou, Yu Wang, Yiran Zong, Tingting Lu, Chunhua Chen
Summary: This paper proposes an autonomous search method for leakage sources in nuclear emergency rescue based on the updated Infotaxis method. By considering factors such as radioactive decay and wet deposition, the method improves search efficiency and accuracy. Experimental results show that the method is particularly effective in searching for leakage sources under high emission rates and provides scientific information for early emergency response and consequence assessment.
NUCLEAR ENGINEERING AND DESIGN
(2024)
Article
Nuclear Science & Technology
Kirill S. Dolganov
Summary: This paper is the first part of a summary overview of IBRAE's work on the severe accident at Unit 1 of Fukushima Daiichi Nuclear Power Station. It focuses on the integral model of Unit 1 and its qualification with available data, including the comparison of simulation results with measurements for the initial phase of the accident. Important issues discussed include the direct modeling of isolation condenser performance and verification of the possibility to use an integral approach to estimate the nuclide inventory in the core.
NUCLEAR ENGINEERING AND DESIGN
(2024)
Article
Nuclear Science & Technology
F. Feria, C. Aguado, J. Benavides, J. Benavides, R. Canencia-Hernanz, M. Cristobal-Beneyto, J. Fernandez Garcia, H. Galan, C. Gonzalez, A. Hernandez-Avellaneda, L. E. Herranz, G. Jimenez, L. Martinez, J. C. Martinez-Murillo, A. Milena-Perez, A. Palacio Alonso, J. Penalva, R. Plaza, D. Perez-Gallego, L. Rey, N. Rodriguez-Villagra, J. Ruiz-Hervias, J. Saiz de Omenaca Tijero, P. Vinas-Pena
Summary: The Spanish R&D efforts in dry interim storage of spent nuclear fuel mainly focus on supporting safety under storage and transportation. Experimental and modelling activities are carried out to understand and predict the fuel response, with major outcomes being improvements in the characterization of dry stored fuel, essential for safety assessment of the back-end fuel cycle.
NUCLEAR ENGINEERING AND DESIGN
(2024)
Article
Nuclear Science & Technology
Ang Li, Yuqing Chen, Yuxian Rao, Qi Cai, Cong Wang
Summary: This paper focuses on the boiling heat transfer model of mini-channels casing-pipes once-through steam generator (MCOTSG). By calibrating and analyzing the different nucleate boiling heat transfer models based on steady state experimental results, the secondary loop heat transfer characteristics and overall operating characteristics of OTSG under feedwater flow rate reduction are simulated. The results can provide a basis for the safety analysis and optimal design of MCOTSG and small modular reactor under low flow rate conditions.
NUCLEAR ENGINEERING AND DESIGN
(2024)
Article
Nuclear Science & Technology
Shu Soma, Masahiro Ishigaki, Satoshi Abe, Yasuteru Sibamoto
Summary: In this paper, the analytical wall function approach was applied to analyze the condensation flow of steam/air mixtures, and good predictions were obtained through CFD analysis.
NUCLEAR ENGINEERING AND DESIGN
(2024)
Article
Nuclear Science & Technology
Jinho Song, Sungjoong Kim
Summary: In this study, a machine learning platform is proposed to assist operators in diagnosing the progression of severe accidents and predicting key parameters using long short term memory networks and MELCOR simulation data. The platform shows reasonable accuracy in predicting both similar and unseen test data, as well as lost signals and key parameters for accident management.
NUCLEAR ENGINEERING AND DESIGN
(2024)
Article
Nuclear Science & Technology
Liang Zhao, Zhengbai Chang, Chulin Mai, Hong Ran, Jin Jiang
Summary: This study investigates the dynamic characteristics, valve disc motion, and flow field of a nozzle check valve under different spring stiffness and fluid deceleration rates. Experimental tests and numerical simulations were performed to analyze the effects on various parameters during the dynamic closing process of the valve. The results provide insights for the optimization design of check valves and more accurate calculation of their dynamic characteristic curves.
NUCLEAR ENGINEERING AND DESIGN
(2024)
Article
Nuclear Science & Technology
Xun Lan, Yanbo Jiang, Dan Sun, Wenbo Liu, Wenjie Li
Summary: In this study, a three-dimensional phase-field model was developed to investigate the evolution of intergranular bubbles during irradiation. The study examined the dependency of bubble percolation on bubble shape, fission rate, and average grain size. The simulation results revealed the significant effects of these factors on the shape of GB bubbles, the percolation rate, and the connectivity threshold of GB bubbles.
NUCLEAR ENGINEERING AND DESIGN
(2024)
Article
Nuclear Science & Technology
J. M. S. Mendes, A. Heimlich, A. M. M. De Lima, F. C. Silva
Summary: An algorithm for solving the constitutive equations of the fourth-order Nodal Expansion Method (NEM) in parallel using GPU with quadratic transverse leakage has been proposed. The algorithm, implemented in CUDA language, showed comparable accuracy and reduced execution time compared to the CNFR code. This algorithm and the developed program have potential use in the optimization process of nuclear fuel reload patterns.
NUCLEAR ENGINEERING AND DESIGN
(2024)
Article
Nuclear Science & Technology
M. Jafari, H. Jafari, M. H. Choopan Dastjerdi, J. Mokhtari
Summary: This study investigates the ability of the PGNAA facility of the Isfahan MNSR reactor to measure boron concentration in solution samples. A measurement system model is developed using Monte Carlo calculation, and a cadmium sheet is used to reduce the effect of boron in the shield. The accuracy of the model is verified through experimental tests, resulting in a calibration curve.
NUCLEAR ENGINEERING AND DESIGN
(2024)
Article
Nuclear Science & Technology
Ibrahim Gad-el-Hak, Njuki Mureithi, Kostas Karazis, Brian Painter
Summary: This study investigates the risk of fluidelastic instability induced by degraded baffle-former bolts in a nuclear fuel assembly. Experimental results show that the stability threshold of the mock-up array strongly depends on the relative position of the jet flow with respect to the array centerline, and axial flow velocity also has a significant effect on the jet-induced instability.
NUCLEAR ENGINEERING AND DESIGN
(2024)
Article
Nuclear Science & Technology
Yuhang Niu, Scolaro Alessandro, Carlo Fiorina, Hao Qin, Gauthier Lazare, Yingwei Wu, Wenxi Tian, G. H. Su
Summary: This paper presents the incorporation of DNB prediction into the GeN-Foam code, which is based on OpenFOAM. The accuracy of GeN-Foam in modeling DNB conditions in PWR was assessed through validation against experimental data and other codes. The results show that GeN-Foam exhibits good performance in simulating two-phase flow boiling conditions and accurately predicts the occurrence of DNB.
NUCLEAR ENGINEERING AND DESIGN
(2024)