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Proceedings Papers

Application of Hybrid Subgroup Decomposition Method to Gas Cooled Thermal Reactor Problem

Saam Yasseri, Farzad Rahnema
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T11A005, July 7–11, 2014
Paper No: ICONE22-30353
DOI: https://doi.org/10.1115/ICONE22-30353
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Topics: Eigenvalues, Thermal reactors
Proceedings Papers

Development of Grid Depression Model for GalaxyCosmo-S

Hiroki Koike, Kazuki Kirimura, Kazuya Yamaji, Shinya Kosaka, Hideki Matsumoto
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T11A006, July 7–11, 2014
Paper No: ICONE22-30379
DOI: https://doi.org/10.1115/ICONE22-30379
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Topics: Cycles, Design, Fittings, Fuels, Manufacturing, Nuclear design, Pressurized water reactors, Sensors, Uncertainty
Proceedings Papers

Comparison Between PARCS and MCNP6 Codes on VVER1000/V320 Core

Guido Mazzini, Bruno Miglierini, Marek Ruščák
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T11A007, July 7–11, 2014
Paper No: ICONE22-30386
DOI: https://doi.org/10.1115/ICONE22-30386
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Topics: Accidents, Boron, Cross section (Physics), Design, Engineering simulation, Neutrons, Nuclear power stations, Nuclear reactor kinetics, Pressurized water reactors, Safety
Proceedings Papers

A Time-Dependent Solver for Coupled Neutron-Transport Thermal-Mechanics Calculations and Simulation of a Godiva Prompt-Critical Burst

Carlo Fiorina, Manuele Aufiero, Sandro Pelloni, Konstantin Mikityuk
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T11A008, July 7–11, 2014
Paper No: ICONE22-30395
DOI: https://doi.org/10.1115/ICONE22-30395
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Topics: Neutrons, Simulation, Transients (Dynamics), Uranium, Collaboration, Computer software, Fluid dynamics, Manufacturing, Physics, Slabs
Proceedings Papers

Analysis of Isotopic Contributions to Doppler Coefficients of Inert Matrix Fuels

Jinsen Xie, Tao Yu
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T11A009, July 7–11, 2014
Paper No: ICONE22-30620
DOI: https://doi.org/10.1115/ICONE22-30620
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Topics: Fuels, Neutrons, Absorption, Resonance, Hazards, Isotopes, Pressurized water reactors, Temperature, Weapons, Zirconium
Proceedings Papers

233 U Evaluation Comparison Study

Mohammad Alrwashdeh, Aniseh Abdalla, Kan Wang
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T11A001, July 7–11, 2014
Paper No: ICONE22-30057
DOI: https://doi.org/10.1115/ICONE22-30057
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Topics: Bayes methods, Computers, Cross section (Physics), Databases, Fittings, Resonance
Proceedings Papers

Application of 3D Coupled Code SPARKLE-2 to PWR Anticipated Transient Without Scram

Koji Asano, Hikaru Sakamoto, Satoshi Imura, Junto Ogawa
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T11A010, July 7–11, 2014
Paper No: ICONE22-30744
DOI: https://doi.org/10.1115/ICONE22-30744
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Topics: Pressurized water reactors, Scram, Transients (Dynamics), Failure, Pressure, Design, Feedback, Feedwater, Flow (Dynamics), Neutrons
Proceedings Papers

Monte Carlo Neutron Transport on GPUs

Ryan M. Bergmann, Jasmina L. Vujić
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T11A002, July 7–11, 2014
Paper No: ICONE22-30148
DOI: https://doi.org/10.1115/ICONE22-30148
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Topics: Graphics processing units, Neutrons, Algorithms, Energy consumption, Architecture, Engineering simulation, Lumber, Power stations, Simulation
Proceedings Papers

ANDREA 2: Improved Version of Code for Reactor Core Analysis

František Havlůj, Radim Vočka, Jiří Vysoudil
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T11A011, July 7–11, 2014
Paper No: ICONE22-30840
DOI: https://doi.org/10.1115/ICONE22-30840
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Topics: Physics, Workflow
Proceedings Papers

A 1D Monoenergetic Neutron Transport Benchmark in an Infinite Medium

Barry D. Ganapol
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T11A003, July 7–11, 2014
Paper No: ICONE22-30156
DOI: https://doi.org/10.1115/ICONE22-30156
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Topics: Neutrons, Approximation, Engineering simulation, Matlab, Simulation
Proceedings Papers

Physical Analysis of LBE Spallation Target Coupled With the Reactor for CIADS

Lu Zhang, Yongwei Yang, Yucui Gao
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T11A004, July 7–11, 2014
Paper No: ICONE22-30195
DOI: https://doi.org/10.1115/ICONE22-30195
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Topics: Spallation (Nuclear physics), Density, Design, Neutrons, Pipes, Heat, Neutron flux, Optimization, Physics, Thermal hydraulics
Proceedings Papers

The Super Equivalence Method in Monte Carlo Based Homogenization

Mancang Li, Kan Wang, Dong Yao
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T11A012, July 7–11, 2014
Paper No: ICONE22-30882
DOI: https://doi.org/10.1115/ICONE22-30882
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Topics: Chemical kinetics, Cross section (Physics), Diffusion (Physics), Eigenvalues, Errors, Light water reactors, Monte Carlo methods, Physics, Preservation
Proceedings Papers

Time-Dependent, Three Dimensional Nodal Transport Code Development Based on Unstructured Mesh

Mingtao He, Hongchun Wu, Liangzhi Cao, Youqi Zheng, ShengCheng Zhou
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T11A014, July 7–11, 2014
Paper No: ICONE22-31018
DOI: https://doi.org/10.1115/ICONE22-31018
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Topics: Approximation, Geometry, Neutrons, Spacetime, Transients (Dynamics), Transport processes
Proceedings Papers

Monte Carlo Burn-Up Code System MCADS and its Application

Xuesong Yan, Ji Qi, Lei Yang, Xunchao Zhang, Yaling Zhang
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T11A013, July 7–11, 2014
Paper No: ICONE22-30948
DOI: https://doi.org/10.1115/ICONE22-30948
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Topics: Fast neutron reactors, Fuels, Isotopes, Pressurized water reactors
Proceedings Papers

Cross Sections Influence on Monte Carlo Based Burnup Codes

Davide Chersola, Guglielmo Lomonaco, Guido Mazzini
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T11A015, July 7–11, 2014
Paper No: ICONE22-31049
DOI: https://doi.org/10.1115/ICONE22-31049
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Topics: Cross section (Physics), Flux (Metallurgy), Nuclides
Proceedings Papers

Physics Analysis of the Accelerator Driven Subcritical Reactor Core

Feng Wang, Xue Qin, Zilong An, Bo Cui
Proc. ASME. ICONE21, Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering, V005T11A010, July 29–August 2, 2013
Paper No: ICONE21-15846
DOI: https://doi.org/10.1115/ICONE21-15846
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Topics: Design, Neutron flux, Neutrons, Particulate matter, Physics
Proceedings Papers

Research on the Measurement of Deep Subcriticality Based on Pulsed Neutron Source Method

Shibiao Pan
Proc. ASME. ICONE21, Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering, V005T11A011, July 29–August 2, 2013
Paper No: ICONE21-15883
DOI: https://doi.org/10.1115/ICONE21-15883
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Topics: Neutron sources, Neutrons, Rods, China, Critical points (Physics), Design, Diffusion (Physics), Measurement systems, Neutron flux, Nuclear power
Proceedings Papers

Stationarity Issues in Monte Carlo Simulation for Neutron Transport

Zafar Ullah Koreshi
Proc. ASME. ICONE21, Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering, V005T11A001, July 29–August 2, 2013
Paper No: ICONE21-15016
DOI: https://doi.org/10.1115/ICONE21-15016
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Topics: Neutrons, Simulation, Cycles, Diffusion (Physics), Entropy, Signal processing, Signals
Proceedings Papers

Startup of In-Hospital Neutron Irradiator

YiGuo Li, Pu Xia, XiaoBo Wu, ShuYun Zou, Dan Peng, Jin Lu, JingYan Hong, ZiZhu Zhang, Tong Liu, YongMao Zhou
Proc. ASME. ICONE21, Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering, V005T11A012, July 29–August 2, 2013
Paper No: ICONE21-15925
DOI: https://doi.org/10.1115/ICONE21-15925
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Topics: Neutron beams, Neutrons
Proceedings Papers

Investigation on the Frequency-Dependent Response of Neutron Noise in 2-D MSR

Jiangmeng Wang, Xinrong Cao
Proc. ASME. ICONE21, Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering, V005T11A002, July 29–August 2, 2013
Paper No: ICONE21-15135
DOI: https://doi.org/10.1115/ICONE21-15135
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Topics: Molten salt reactors, Neutrons, Noise (Sound)