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Proceedings Papers

Numerical Study on the Operational Behavior of Catalytic Components With Spherical Packed Bed Structures

Tianming Man, Zehua Guo, Ming Ding, Wenkai Liang
Proc. ASME. ICONE31, Volume 9: Advanced Methods of Manufacturing for Nuclear Reactors and Components; Severe Accidents and Mitigation Strategies for Beyond Design Basis Events, V009T11A004, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134633
https://doi.org/10.1115/ICONE31-134633
View Paper titled, Numerical Study on the Operational Behavior of Catalytic Components With Spherical Packed Bed Structures
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Topics: Accidents, Catalysts, Chemical kinetics, Computational fluid dynamics, Computer simulation, Computer software, Containment, Explosions, Flow (Dynamics), Hydrogen
Proceedings Papers

Neutronics Analysis of RBMK-1000 Reactor Using OpenMC: Criticality and Depletion Analysis at 3D Assembly Level

Mohammad Hashemi, Rafael Macián-Juan, Martin Ohlerich
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A018, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90636
https://doi.org/10.1115/ICONE29-90636
View Paper titled, Neutronics Analysis of RBMK-1000 Reactor Using OpenMC: Criticality and Depletion Analysis at 3D Assembly Level
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Topics: Manufacturing, Nuclear fission, Spent nuclear fuels, Chemical kinetics, Computer programming languages, Databases, Design, Nuclear power, Nuclear power stations, Parametric design
Proceedings Papers

Implementation and Comparison of Super Homogenization Method Based on Monte Carlo and Deterministic Codes

Yuan Yuan, Guoming Liu, Xiaodong Huo
Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A006, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92520
https://doi.org/10.1115/ICONE29-92520
View Paper titled, Implementation and Comparison of Super Homogenization Method Based on Monte Carlo and Deterministic Codes
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Topics: Chemical kinetics, Cross section (Physics), Fast neutron reactors, Geometry, Manufacturing, Modeling, Physics, Relaxation (Physics), Very high temperature reactors
Proceedings Papers

Modeling of Low-Temperature Reduction of Metal Oxide in Hydrogen Treatment System for Severe Accidents in Nuclear Power Plants

Kotaro Nakamura, Masashi Tanabe, Satoru Abe, Takashi Mawatari, Takao Nakagaki
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A029, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16450
https://doi.org/10.1115/ICONE2020-16450
View Paper titled, Modeling of Low-Temperature Reduction of Metal Oxide in Hydrogen Treatment System for Severe Accidents in Nuclear Power Plants
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Topics: Accidents, Copper, Hydrogen, Low temperature, Metals, Modeling, Nuclear power stations, Oxidation, Explosions, Water vapor
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81316
https://doi.org/10.1115/ICONE26-81316
View Paper titled, Isogeometric Multi-Level Iterative Solution Algorithms With Applications in Nuclear Reactor Physics
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Topics: Algorithms, Nuclear reactors, Physics, Diffusion (Physics), Geometry, Neutrons, Algebra, Chemical kinetics, Construction, Finite element analysis
Proceedings Papers

The Verification of SONG Library

Hua Bei, Jinkun Zhao, Qichang Chen, Shengyi Si
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A036, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66946
https://doi.org/10.1115/ICONE25-66946
View Paper titled, The Verification of SONG Library
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Topics: Absorption, Chemical kinetics, Cladding systems (Building), Electromagnetic scattering, Fuels, Isotopes, Molten salt reactors, Nuclear fission, Pressurized water reactors, Radiation scattering
Proceedings Papers

Development of Hydrogen Treatment System in Severe Accident: Part 2 — Study on Reaction Characteristic of a Hydrogen Processing Unit

Chikako Iwaki, Daigo Kittaka, Toshihiro Yoshii, Motoshige Yagyu, Masato Okamura, Masashi Tanabe, Fumihiko Ishibashi
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T07A012, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60917
https://doi.org/10.1115/ICONE24-60917
View Paper titled, Development of Hydrogen Treatment System in Severe Accident: Part 2 — Study on Reaction Characteristic of a Hydrogen Processing Unit
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Topics: Accidents, Hydrogen, Metals, Pipes, Pressure, Temperature, Vents, Boiling water reactors, Filters, Oxidation
Proceedings Papers

Severe Accident Related Vulnerabilities, Potential Design Enhancements and Opportunities for International Cooperation in Risk Reduction in Pressurized Heavy Water Reactors

Sunil Nijhawan
Proc. ASME. NUCLRF2015, ASME 2015 Nuclear Forum, V001T02A002, June 28–July 2, 2015
Publisher: American Society of Mechanical Engineers
Paper No: NUCLRF2015-49574
https://doi.org/10.1115/NUCLRF2015-49574
View Paper titled, Severe Accident Related Vulnerabilities, Potential Design Enhancements and Opportunities for International Cooperation in Risk Reduction in Pressurized Heavy Water Reactors
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Topics: Accidents, Design, Heavy water reactors, Risk reduction, Fuels, Containment, Hydrogen, Nuclear fission, Pressure, Alternating current (Electricity)
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30882
https://doi.org/10.1115/ICONE22-30882
View Paper titled, The Super Equivalence Method in Monte Carlo Based Homogenization
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Topics: Chemical kinetics, Cross section (Physics), Diffusion (Physics), Eigenvalues, Errors, Light water reactors, Monte Carlo methods, Physics, Preservation
Proceedings Papers

3D Calculations of PWR Vessels Neutron Fluence With EFLUVE 3D Code

Cécile-Aline Gosmain, Sylvain Rollet, Damien Schmitt
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T02A035, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16316
https://doi.org/10.1115/ICONE21-16316
View Paper titled, 3D Calculations of PWR Vessels Neutron Fluence With EFLUVE 3D Code
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Topics: Fluence (Radiation measurement), Neutrons, Pressurized water reactors, Vessels, Neutron sources, Surveillance, Chemical kinetics, Pressure vessels, Dosimeters, Dosimetry
Proceedings Papers

The Transport-Burnup Coupling System Between MCMG-II and STEP1.0 for High Fidelity Calculations

Mingyu Wu, Shixi Wang, Yong Yang, Qiang Zhang, Jiayin Yang
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, V005T11A013, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16077
https://doi.org/10.1115/ICONE21-16077
View Paper titled, The Transport-Burnup Coupling System Between MCMG-II and STEP1.0 for High Fidelity Calculations
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Topics: Algorithms, Chain, Chemical kinetics, Collisions (Physics), Density, Dimensions, Geometry, Neutrons, Nuclear fission, Nuclides
Proceedings Papers

Numerical Simulation of Graphite Oxidation in HTGR

Yao Wang, Peng Wang, Suyuan Yu
Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 373-379, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54669
https://doi.org/10.1115/ICONE20-POWER2012-54669
View Paper titled, Numerical Simulation of Graphite Oxidation in HTGR
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Topics: Computer simulation, Graphite, Oxidation, Very high temperature reactors, Weight (Mass), Accidents, Chemical kinetics, Corrosion, Design, Mass transfer
Proceedings Papers

EFLUVE3D Code: A 3D Tool for the Neutron Fluence Calculations on Pressurized Water Reactor Vessels

Cécile-Aline Gosmain, Sylvain Rollet, Damien Schmitt
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 481-489, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54965
https://doi.org/10.1115/ICONE20-POWER2012-54965
View Paper titled, EFLUVE3D Code: A 3D Tool for the Neutron Fluence Calculations on Pressurized Water Reactor Vessels
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Topics: Fluence (Radiation measurement), Neutrons, Pressurized water reactors, Vessels, Neutron sources, Surveillance, Dosimeters, Pressure vessels, Chemical kinetics, Dosimetry
Proceedings Papers

Kinetic Study of Sodium-Water Reaction Phenomena by Differential Thermal Analysis

Shin Kikuchi, Hiroshi Seino, Akikazu Kurihara, Hiroyuki Ohshima
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 281-289, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54134
https://doi.org/10.1115/ICONE20-POWER2012-54134
View Paper titled, Kinetic Study of Sodium-Water Reaction Phenomena by Differential Thermal Analysis
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Topics: Sodium, Thermal analysis, Water, Sodium fast reactors, Temperature, Heat transfer, Safety, Boilers, Chemical kinetics, Chemical reactions
Proceedings Papers

Study of Self-Shielding Calculation With Temperature Distribution Applying Wavelets Scaling Function Expansion Continuous-Energy Resonance Method

Weiyan Yang, Hongchun Wu, Liangzhi Cao
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 143-150, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29498
https://doi.org/10.1115/ICONE18-29498
View Paper titled, Study of Self-Shielding Calculation With Temperature Distribution Applying Wavelets Scaling Function Expansion Continuous-Energy Resonance Method
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Topics: Resonance, Temperature distribution, Wavelets, Temperature, Cross section (Physics), Fuel rods, Interpolation, Chemical kinetics, Doppler effect, Fuels
Proceedings Papers

Steam-Reheat Options for Pressure-Tube SCWRs

Eugene Saltanov, Wargha Peiman, Amjad Farah, Krysten King, Maria Naidin, Igor Pioro
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 755-766, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29972
https://doi.org/10.1115/ICONE18-29972
View Paper titled, Steam-Reheat Options for Pressure-Tube SCWRs
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Topics: Pressure, Steam, Supercritical water reactors, Nuclear reactors, Nuclear power stations, Water, Temperature, Thermal efficiency, Boilers, Boiling
Proceedings Papers

CFD Simulation of Passive Auto-Catalytic Recombiner Operational Behaviour

S. Kelm, W. Jahn, E.-A. Reinecke, J. Baggemann, H.-J. Allelein
Proc. ASME. ICONE17, Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control, 633-639, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75831
https://doi.org/10.1115/ICONE17-75831
View Paper titled, CFD Simulation of Passive Auto-Catalytic Recombiner Operational Behaviour
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Topics: Accidents, Catalysts, Chemical kinetics, Combustion, Computational fluid dynamics, Computer simulation, Containment, Databases, Failure, Flow (Dynamics)
Proceedings Papers

Steam-Reheat Option for SCWRs

Eugene Saltanov, Romson Monichan, Elina Tchernyavskaya, Igor Pioro
Proc. ASME. ICONE17, Volume 4: Codes, Standards, Licensing and Regulatory Issues; Student Paper Competition, 775-784, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-76061
https://doi.org/10.1115/ICONE17-76061
View Paper titled, Steam-Reheat Option for SCWRs
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Topics: Steam, Supercritical water reactors, Pressure, Nuclear reactors, Nuclear power stations, Water, Temperature, Thermal efficiency, Boilers, Chemical kinetics
Proceedings Papers

Modeling of Hydrogen-Air Detonations in the TONUS CFD Code and Its Application to the FLAME F-19 Test

Eveliina Takasuo
Proc. ASME. ICONE16, Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 717-725, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48614
https://doi.org/10.1115/ICONE16-48614
View Paper titled, Modeling of Hydrogen-Air Detonations in the TONUS CFD Code and Its Application to the FLAME F-19 Test
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Topics: Computational fluid dynamics, Explosions, Flames, Hydrogen, Modeling, Combustion, Shock (Mechanics), Accident management, Chemical kinetics, Chemically reactive flow
Proceedings Papers

SCW Pressure-Channel Nuclear Reactors: Some Design Features and Concepts

R. B. Duffey, I. L. Pioro, B. A. Gabaraev, Yu. N. Kuznetsov
Proc. ASME. ICONE14, Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy, 643-652, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89609
https://doi.org/10.1115/ICONE14-89609
View Paper titled, SCW Pressure-Channel Nuclear Reactors: Some Design Features and Concepts
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Topics: Design, Nuclear reactors, Pressure, Nuclear power stations, Steam, Water, Temperature, Boilers, Chemical kinetics, Circuits