Numerical Simulation Study on the Air/Water Counter- current Flow Limitation in Nuclear Reactors by youssef morghi, Amir Zacarias Mesquita

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Representativity studies of GEN-III large cores to ZPR experiments with respect to nuclear data by Njayou Tsepeng Eric Karson, Blaise Patrick, Couyras David, Argaud Jean-Philippe, Clouvel Laura, Dos Santos Nicolas

“…Uncertainty quantification plays a crucial role in demonstrating the safety of nuclear reactors by assessing and accounting for the various sources of uncertainty in reactor performance predictions. …”
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Pore size characterization of Cretaceous ironstone by low-field nuclear magnetic resonance technique by A.A. Ige-Adeyeye, O.B. Olatinsu, V.C. Ozebo, L. Esteban

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Conceptual basis for organizing the decommissioning a nuclear power plant based on a reactor unit by Kuznetsov Vladimir, Spiridonov Valery, Derevyashkin Igor, Bukreeva Tatiana, Chebotareva Ksenia, Shinkareva Olga

“…The lack of funds, technologies, radioactive substance storage facilities, spent nuclear fuel processing technologies and specialists in the field of decommissioning impose a restraining imprint on the decommissioning process. …”
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Quantitative evaluation of grooves in fuel ice layers of ICF based on deep learning and x-ray phase retrieval by Kaijun Shi, Kai Wang, Xin Wang, Ji Yan, Baolu Yang, Cheng Yang, Mingtao Li, Mingxun Wang, Jie Xu, Fei Dai, Xing Zhang, Zhanshan Wang, Baozhong Mu

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Removal of fuel retention by direct-current glow discharge under strong magnetic field in EAST superconducting tokamak by Hao Sun, Yaowei Yu, Bin Cao, Guizhong Zuo, Jiansheng Hu

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Multiphysics Computational Modeling of Nuclear Reactors Small Size Through the Coupling of Serpent Codes and Fluent by Erik Lago, Dany Sanchez Dominguez, Leorlen Rojas Mazaíra

“…The study of nuclear energy using computational codes has been widely explored by nuclear engineering researchers through various calculations over the years, with emphasis on neutron and thermo-hydraulic calculations. …”
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Developing a dynamic combined power quality index for assessing the performance of a nuclear facility by Asmaa M. Elsotohy, Mohammed Hamouda Ali, Ahmed S. Adail, Ayman A. Eisa, El-said A Othman

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From the top: surface-derived carbon fuels greenhouse gas production at depth in a peatland by A. Hedgpeth, A. Hedgpeth, A. M. Hoyt, K. C. Cavanaugh, K. J. McFarlane, D. F. Cusack, D. F. Cusack, D. F. Cusack

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Tribological properties of polymer like carbon coatings on NBG-18 nuclear graphite under nitrogen environment by HAN Hai, LIU Huichuan, CHENG Jinjuan, CHEN Xinchun, LIU Pengxiao, QI Wei, TANG Xian

“…This friction generates a considerable amount of graphite dust, which poses a risk to the proper functioning of nuclear reactors.PurposeThis study aims to address the issues of friction and wear experienced by nuclear graphite on the surface of spherical fuel elements in HTGR by utilizing surface modification technology to enhance the mechanical and tribological properties of NBG-18 nuclear graphite.MethodsFirstly, NBG-18 graphite, sourced from SGL Group-The Carbon Company, Germany, was cut into blocks with dimensions of 20 mm×20 mm×5 mm, and a polymer-like carbon (PLC) coating was applied to NBG-18 nuclear graphite using a high-energy ion beam deposition (IBD) process with preprocessing of cleaning, sample loading, vacuuming, transition layer deposition, functional layer deposition, and sampling, resulting in a total coating thickness of approximately 400 nm. …”
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Uncertainty Analysis and Benchmark for Nuclear Criticality Safety Experiment about Uranium Solution Multiple-unit System by ZHOU Qi1, XIA Zhaodong1, CHENG Yuting1, SUN Xu1, WANG Fan1, LI Dongpeng1, 2, LI Huanxing1, ZHANG Zhenyang1, ZHU Qingfu1

“…To increasing the production efficiency of nuclear fuel cycle, processing equipment with fissile materials is arranged closer to each other than before. …”

Study on the effects of initial ice layer and temperature distribution on the redistribution of D2 fuel layer in a cryogenic target by Yina Yao, Guanhua Chen, Wei Lin, Kai Wang, Hui Zhang, Fei Dai

“…Inertial confinement fusion (ICF) is one of the primary methods for achieving controlled nuclear fusion, which is closely related to energy security and national security. …”
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Hydraulics Performance of SDMS-350-8 Single-multistage CentrifugalExtractor with High Flux for Nuclear Applications by XING Yuntong, YANG Xinwei, CHEN Yong, WANG Bo

“…At present, the nuclear fuel reprocessing process that has been realized engineering application is to separate different metal ions by using different partition coefficients of metal ions in extractants. …”

Research on Equivalent One-Dimensional Cylindrical Modeling Method for Lead–Bismuth Fast Reactor Fuel Assemblies by Jinjie Xiao, Yongfa Zhang, Song Li, Ling Chen, Jiannan Li, Cong Zhang

“…The lead-cooled fast reactor (LFR), a Generation IV nuclear system candidate, presents unique neutronic characteristics distinct from pressurized water reactors. …”
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Reprocessing Exhaust Gas Xenon Isotope Correlation Spent Fuel Burn-Up Based on ORIGEN Code by Sheng-hui HUANG, Chang-kun XU, Hao-dong SHAN, Yan CHEN, Li-li LI, Yong-gang ZHAO

“…This study focuses on the measurement needs of spent fuel burn-up during the chopping and dissolution processes of the spent fuel, and conducted research on stable xenon isotope correlation spent fuel burn-up technique. …”
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On material and energy sources of formation of fuel-containing materials during Chernobyl NPP UNIT 4 accident by O. V. Mikhailov

“…Quantitative estimate is given for spent nuclear fuel’ afterheat in a number of other heat energy sources in reactor vault. …”
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Coupled Heat-Mass Transport Modelling of Radionuclide Migration from a Nuclear Waste Disposal Borehole by Kaveh Sookhak Lari, Dirk Mallants

“…Disposal of radioactive waste originating from reprocessing of spent research reactor fuel typically includes stainless steel canisters with waste immobilised in a glass matrix. …”
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Neutron Transport Simulations of RBMK Fuel Assembly Using Multigroup and Continuous Energy Data Libraries within the SCALE Code by Andrius Slavickas, Raimondas Pabarčius, Aurimas Tonkūnas, Sigitas Rimkevičius

“…The results of RBMK-1500 fuel assembly simulations using standard and user-defined DFs were compared. …”
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Multi-physics Coupling within Chalk River Unidentified Deposit on Pressurized Water Reactor Fuel Rod by GAO Quanyi1, CONG Tenglong1, , TIAN Hongkang1, LIU Maolong2, GU Hanyang1

Research on Primary Knock-on Atom and DPA Calculation in SiC Fuel Clad of Micro Gas-cooled Reactor by WANG Ziqi, GUAN Jingyu, DONG Duo, ZHANG Chenglong, ZHU Siyang, HE Kai, LIU Guoming

“…The micro gas-cooled reactor is one kind of advanced movable micro nuclear power devices with very high inherent safety, which adopts a new type of dispersed multi-coated particle fuel mainly made of silicon carbide (SiC) in fuel system. …”