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Proceedings Papers

Foreseen Capabilities, Bottlenecks Identification and Potential Limitations of Serpent MC Transport Code in Large-Scale Full 3-D Burnup Calculations

Diego Ferraro, Manuel Garcia, Luigi Mercatali, Victor Hugo Sanchez Espinoza, Jaakko Leppänen, Ville Valtavirta
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A049, July 22–26, 2018
Paper No: ICONE26-82305
DOI: https://doi.org/10.1115/ICONE26-82305
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Topics: Architecture, Design, Fuels, Innovation, Light water reactors, Nuclear industry, Nuclear reactors, Physics, Safety, Steady state
Proceedings Papers

Analysis on Pellet-Cladding Interaction of Fuel Rod During Power Ramp of NHR200-II

Tianshan Kang, Songyang Li, Dingqu Wang, Yueyuan Jiang, Weihua Li
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A029, July 22–26, 2018
Paper No: ICONE26-81596
DOI: https://doi.org/10.1115/ICONE26-81596
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Topics: Cladding systems (Building), Fuel rods, Risk, Computer software, Damage, Heat transfer, Nuclear reactors, Pressure, Safety, Simulation
Proceedings Papers

Physics Design of Special Epithermal Neutron Beam Based on Multi D-D Reaction Neutron Tubes

Yi Yang, Yiguo Li, Bin Zhao
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A019, July 22–26, 2018
Paper No: ICONE26-81392
DOI: https://doi.org/10.1115/ICONE26-81392
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Topics: Design, Neutron beams, Neutrons, Physics, Irradiation (Radiation exposure), Neutron sources, Contamination, Neutron generators, Boron, Cancer
Proceedings Papers

Isogeometric Multi-Level Iterative Solution Algorithms With Applications in Nuclear Reactor Physics

C. Latimer, J. Kópházi, M. D. Eaton
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A014, July 22–26, 2018
Paper No: ICONE26-81316
DOI: https://doi.org/10.1115/ICONE26-81316
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Topics: Algorithms, Nuclear reactors, Physics, Diffusion (Physics), Geometry, Neutrons, Algebra, Chemical kinetics, Construction, Finite element analysis
Proceedings Papers

Application of the Dynamic Rod Worth Measurement Method on WWER

Wenbo Zhao, Zhumin Jiang, Liangzi Wang, Chenlin Wang, Yingrui Yu, Zhaohu Gong, Minxiao Zhong, Tongxian Liu, Hongzhi Xiang
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A003, July 22–26, 2018
Paper No: ICONE26-81055
DOI: https://doi.org/10.1115/ICONE26-81055
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Topics: Boron, Dynamics (Mechanics), Geometry, Monte Carlo methods, Neutrons, Nuclear power stations, Pressurized water reactors, Sensors, Shapes, Spacetime
Proceedings Papers

Preliminary Study on Thermal Performance of Inert Matrix Disperse Pellet Using FEA Method

Lu Zhiwei, Li Yun, Zhang Yongdong, Li Lei, Ma Zhaodandan, Liu Tong
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A044, July 22–26, 2018
Paper No: ICONE26-82191
DOI: https://doi.org/10.1115/ICONE26-82191
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Topics: Finite element analysis, Fuels, Light water reactors, Thermal conductivity, Accidents, China, Gas cooled reactors, Heat transfer, High temperature, Nuclear fuels
Proceedings Papers

Uranium Enrichment Measurement Using Enrichment-Meter Approach

K. Abd El Gawad, Yushou Song
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A039, July 22–26, 2018
Paper No: ICONE26-82101
DOI: https://doi.org/10.1115/ICONE26-82101
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Topics: Uranium, Containers, Simulation, Accuracy and precision, Wall thickness, Calibration, Dimensions, Equilibrium (Physics), Gamma ray spectrometry, Germanium
Proceedings Papers

Severe Accident Analysis for Reactor Core Applying SiC to Fuel Claddings and Channel Boxes

Hideki Horie, Yutaka Takeuchi, Kenya Takiwaki, Fumie Sebe, Kazuo Kakiuchi, Hisaki Sato
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A034, July 22–26, 2018
Paper No: ICONE26-81923
DOI: https://doi.org/10.1115/ICONE26-81923
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Topics: Accidents, Fuels, Oxidation, Cladding systems (Building), High temperature, Hydrogen, Nuclear power stations, Temperature, Chemical reactions, Damage
Proceedings Papers

Assessment of Failure Modes of Monolithic Fuel Plates

Hakan Ozaltun, Pavel G. Medvedev, Barry H. Rabin
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A055, July 22–26, 2018
Paper No: ICONE26-82437
DOI: https://doi.org/10.1115/ICONE26-82437
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Topics: Failure mechanisms, Fuels, Plates (structures), Failure, Irradiation (Radiation exposure), Tension, Fuel systems, Porosity, Simulation results, Thermomechanics
Proceedings Papers

Development and Verification of a New Nuclear Data Processing System NECP-Atlas

Jialong Xu, Tiejun Zu, Liangzhi Cao, Hongchun Wu
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A024, July 22–26, 2018
Paper No: ICONE26-81516
DOI: https://doi.org/10.1115/ICONE26-81516
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Topics: Information processing systems, Computational physics, Nuclear engineering
Proceedings Papers

Influence of Xe-135 Dynamic Behavior on Core Operation Safety for a Molten Salt Reactor

Wu Jian-hui, Li Xiao-xiao, Hu Ji-feng, Chen Jin-gen, Yu Cheng-gang, Zou Chun-yan, Cai Xiang-zhou
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A050, July 22–26, 2018
Paper No: ICONE26-82352
DOI: https://doi.org/10.1115/ICONE26-82352
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Topics: Molten salt reactors, Safety, Neutrons, Fuels, Helium, Nuclear reactors, Absorption, Chain, Computational methods, Density
Proceedings Papers

Modelling and Simulation Activities in Support of the UK Nuclear R&D Programme on Digital Reactor Design

B. Lindley, D. Allen, J. Lillington, A. Smethurst, P. Smith, D. Bowman, L. Dwyer, K. Lai, A. Levers, K. Vikhorev, D. Litskevich, B. Merk, E. Patelli, E. Patterson, M. Bankhead, A. Peakman, S. de Haas, C. Jackson, J. Draup, E. Galenne, G. Parks, E. Shwageraus, M. D. Eaton
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A004, July 22–26, 2018
Paper No: ICONE26-81090
DOI: https://doi.org/10.1115/ICONE26-81090
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Topics: Design, Modeling, Simulation, Pressurized water reactors, Physics, Bricks, Graphite, Nuclear design
Proceedings Papers

Experimental and Modeling Research on Leading Betavoltaic Technology

Thomas E. Adams, Shripad T. Revankar, Darrell S. Cheu, Peter Cabauy, Jesse Grant, Bret Elkind
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A056, July 22–26, 2018
Paper No: ICONE26-82475
DOI: https://doi.org/10.1115/ICONE26-82475
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Topics: Modeling, Electrolytes, Leakage, Temperature, Corrosion, Defense industry, Electronics, Explosions, Fire, Hazards
Proceedings Papers

Greatly Enhanced Thermal Conductivity of Fully Inert Matrix Dispersion Pellet (IMDP) Produced by Spark Plasma Sintering (SPS) Technique

Zhaodandan Ma, Tong Liu, Rui Li, Maozhou Sun, Zhiwei Lu
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A057, July 22–26, 2018
Paper No: ICONE26-82536
DOI: https://doi.org/10.1115/ICONE26-82536
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Topics: Plasmas (Ionized gases), Sintering, Thermal conductivity, Fuels, Temperature, Finite element methods, Finite element model, Geometry, Heat capacity, High temperature
Proceedings Papers

First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM

Alessandro Scolaro, Ivor Clifford, Carlo Fiorina, Andreas Pautz
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A051, July 22–26, 2018
Paper No: ICONE26-82381
DOI: https://doi.org/10.1115/ICONE26-82381
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Topics: Nuclear fuels, Temperature, Electrical conductance, Fuels, Materials properties, Cracking (Materials), Creep, Databases, Fracture (Process), Fuel rods
Proceedings Papers

Towards Development of Uncertainty Library for Nuclear Reactor Core Simulation

Hany S. Abdel-Khalik, Dongli Huang, Ondrej Chvala, G. Ivan Maldonado
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A052, July 22–26, 2018
Paper No: ICONE26-82385
DOI: https://doi.org/10.1115/ICONE26-82385
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Topics: Nuclear reactors, Simulation, Uncertainty, Physics, Algorithms, Boiling water reactors, Cross section (Physics), Degrees of freedom, Modeling, Uncertainty quantification
Proceedings Papers

Experimental Research and Development of Safety Analysis Systems for Advanced Types of Fuel Rods

Alexander I. Maximkin, Ivan S. Kryukov, Alexander N. Ableev, Alexander V. Berestov, Ilya I. Rodko
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A053, July 22–26, 2018
Paper No: ICONE26-82387
DOI: https://doi.org/10.1115/ICONE26-82387
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Topics: Fuel rods, Industrial research, Safety, Fuels, Reliability, Cladding systems (Building), Cycles, Failure, Instrumentation, Leakage
Proceedings Papers

Internal Coupling Between Neutronics and Thermal-Hydraulics With RMC/CTF and Validation Using VERA Benchmarks

Kaiwen Li, Shichang Liu, Juanjuan Guo, Kan Wang
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A054, July 22–26, 2018
Paper No: ICONE26-82397
DOI: https://doi.org/10.1115/ICONE26-82397
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Topics: Manufacturing, Thermal hydraulics, Virtual reality
Proceedings Papers

Parallel Computation of the Point Neutron Kinetic Equations Using Parallel Revisionist Integral Deferred Correction

Yun Cai, Xingjie Peng, Qing Li, Zhizhu Zhang, Zhumin Jiang, Guo Rui
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A010, July 22–26, 2018
Paper No: ICONE26-81205
DOI: https://doi.org/10.1115/ICONE26-81205
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Topics: Computation, Errors, Neutrons, Safety
Proceedings Papers

Analysis and Improvement of Global-Local Self-Shielding Calculation Scheme for AIC Control Rods

Jikui Li, Tiejun Zu, Liangzhi Cao, HongChun Wu, Qingming He
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A045, July 22–26, 2018
Paper No: ICONE26-82196
DOI: https://doi.org/10.1115/ICONE26-82196
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Topics: Rods, Resonance, Errors, Absorption, Fuels, Cross section (Physics), Neutrons, Nuclear reactors, Nuclides, Physics