1-20 of 97
Breeder reactors
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Proceedings Papers

Development and Assessment of a Nearly Autonomous Management and Control System During a Single Loss of Flow Accident

Linyu Lin, Paridhi Athe, Pascal Rouxelin, Nam Dinh, Jeffrey Lane
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T06A033, August 4–5, 2020
Paper No: ICONE2020-16908
https://doi.org/10.1115/ICONE2020-16908
View Paper titled, Development and Assessment of a Nearly Autonomous Management and Control System During a Single Loss of Flow Accident
Open the PDF for Development and Assessment of a Nearly Autonomous Management and Control System During a Single Loss of Flow Accident in another window
Topics: Accidents, Control systems, Flow (Dynamics), Workflow, Databases, Safety, Breeder reactors, Decision making, Design, Engines
Proceedings Papers

Core Design Study of Super FBR With Multi-Axial Fuel Shuffling and Different Coolant Density

Shogo Noda, Sukarman Sukarman, Akifumi Yamaji, Tetsuo Takei, Takanari Fukuda, Arisa Ayukawa
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A011, July 22–26, 2018
Paper No: ICONE26-81501
https://doi.org/10.1115/ICONE26-81501
View Paper titled, Core Design Study of Super FBR With Multi-Axial Fuel Shuffling and Different Coolant Density
Open the PDF for Core Design Study of Super FBR With Multi-Axial Fuel Shuffling and Different Coolant Density in another window
Topics: Coolants, Density, Design, Fuels, Breeder reactors, Collisions (Physics), Neutron flux, Neutrons, Probability, Temperature
Proceedings Papers

Validation of a Code and Effect of Turbulence Model on Predicting Thermal Stratification Phenomena in the Upper Plenum of SFR

Shibao Wang, Dalin Zhang, Chenglong Wang, Ping Song, Jing Chen, Suizheng Qiu, Guanghui Su
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A035, July 22–26, 2018
Paper No: ICONE26-81551
https://doi.org/10.1115/ICONE26-81551
View Paper titled, Validation of a Code and Effect of Turbulence Model on Predicting Thermal Stratification Phenomena in the Upper Plenum of SFR
Open the PDF for Validation of a Code and Effect of Turbulence Model on Predicting Thermal Stratification Phenomena in the Upper Plenum of SFR in another window
Topics: Sodium fast reactors, Thermal stratification, Turbulence, Sodium, Momentum, Breeder reactors, Buoyancy, Convection, Deformation, Diffusion (Physics)
Proceedings Papers

Development of Evaluation Method for Cold Trap in Fast Breeder Reactor: Part 2 — Analytical Evaluation of Impurity Capturing Capacity in Cold Trap

Shiro Takahashi, Akinori Tamura, Hiroyuki Nakata, Akio Takota
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A109, July 2–6, 2017
Paper No: ICONE25-67699
https://doi.org/10.1115/ICONE25-67699
View Paper titled, Development of Evaluation Method for Cold Trap in Fast Breeder Reactor: Part 2 — Analytical Evaluation of Impurity Capturing Capacity in Cold Trap
Open the PDF for Development of Evaluation Method for Cold Trap in Fast Breeder Reactor: Part 2 — Analytical Evaluation of Impurity Capturing Capacity in Cold Trap in another window
Topics: Breeder reactors, Evaluation methods, Hydrogen, Sodium, Computational fluid dynamics, Oxygen, Sodium compounds, Wire, Packing (Shipments), Packings (Cushioning)
Proceedings Papers

Development of Evaluation Method for Cold Trap in Fast Breeder Reactor: Part 1 — Numerical Analysis of Impurity Precipitation on Mesh Wire

Akinori Tamura, Shiro Takahashi, Hiroyuki Nakata, Akio Takota
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A110, July 2–6, 2017
Paper No: ICONE25-67702
https://doi.org/10.1115/ICONE25-67702
View Paper titled, Development of Evaluation Method for Cold Trap in Fast Breeder Reactor: Part 1 — Numerical Analysis of Impurity Precipitation on Mesh Wire
Open the PDF for Development of Evaluation Method for Cold Trap in Fast Breeder Reactor: Part 1 — Numerical Analysis of Impurity Precipitation on Mesh Wire in another window
Topics: Breeder reactors, Evaluation methods, Numerical analysis, Precipitation, Wire, Sodium, Sodium compounds, Lattice Boltzmann methods, Reynolds number, Hydrogen
Proceedings Papers

New Exploration on TMSR: Redesign of the TMSR Lattice

Jinkun Zhao, Shengyi Si, Qichang Chen, Hua Bei
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A016, July 2–6, 2017
Paper No: ICONE25-66564
https://doi.org/10.1115/ICONE25-66564
View Paper titled, New Exploration on TMSR: Redesign of the TMSR Lattice
Open the PDF for New Exploration on TMSR: Redesign of the TMSR Lattice in another window
Topics: Breeder reactors, Ceramics, Cladding systems (Building), Coolants, Corrosion, Design, Fast neutron reactors, Flow (Dynamics), Fluids, Fuels
Proceedings Papers

Breeding Properties Study on High Power Thorium Molten Salt Reactor

Yafen Liu, Rui Guo, Xiangzhou Cai, Rui Yan, Yang Zou, Bo Zhou
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A026, July 2–6, 2017
Paper No: ICONE25-66961
https://doi.org/10.1115/ICONE25-66961
View Paper titled, Breeding Properties Study on High Power Thorium Molten Salt Reactor
Open the PDF for Breeding Properties Study on High Power Thorium Molten Salt Reactor in another window
Topics: Molten salt reactors, Breeder reactors, Fluids, Fuels, Generation IV reactors, Security, Temperature, Transients (Dynamics)
Proceedings Papers

Analysis of Sustainable Thorium Fuel Utilization in Molten Salt Reactors Starting From Enriched Uranium

Deyang Cui, Xiangzhou Cai, Jingen Chen, Chenggang Yu
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A033, July 2–6, 2017
Paper No: ICONE25-67177
https://doi.org/10.1115/ICONE25-67177
View Paper titled, Analysis of Sustainable Thorium Fuel Utilization in Molten Salt Reactors Starting From Enriched Uranium
Open the PDF for Analysis of Sustainable Thorium Fuel Utilization in Molten Salt Reactors Starting From Enriched Uranium in another window
Topics: Fuels, Molten salt reactors, Sustainability, Uranium, Nuclear fuel cycle, Light water reactors, Breeder reactors, Energy generation, Energy sustainability, Industrial research
Proceedings Papers

Thermal-Hydraulic Analysis of the EBR-II SHRT-45R Unprotected Loss of Flow Experiment With Modified RELAP5

Tang Simiao, Song Jian, Zhang Dalin, Wang Chenglong, Qiu Suizheng, Su Guanghui, Tian Wenxi
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A023, July 2–6, 2017
Paper No: ICONE25-66766
https://doi.org/10.1115/ICONE25-66766
View Paper titled, Thermal-Hydraulic Analysis of the EBR-II SHRT-45R Unprotected Loss of Flow Experiment With Modified RELAP5
Open the PDF for Thermal-Hydraulic Analysis of the EBR-II SHRT-45R Unprotected Loss of Flow Experiment With Modified RELAP5 in another window
Topics: Flow (Dynamics), Sodium fast reactors, Accidents, Feedback, Coolants, Temperature, Fuels, Pumps, Safety, Sodium
Proceedings Papers

Development and Application of the Neutronics/Thermal-Hydraulics Coupling Code for Safety Analysis of EBR-II Loss of Heat Sink Tests Without Scram

Daogang Lu, Chao Guo, Danting Sui
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T10A025, June 26–30, 2016
Paper No: ICONE24-60862
https://doi.org/10.1115/ICONE24-60862
View Paper titled, Development and Application of the Neutronics/Thermal-Hydraulics Coupling Code for Safety Analysis of EBR-II Loss of Heat Sink Tests Without Scram
Open the PDF for Development and Application of the Neutronics/Thermal-Hydraulics Coupling Code for Safety Analysis of EBR-II Loss of Heat Sink Tests Without Scram in another window
Topics: Heat sinks, Safety, Scram, Thermal hydraulics, Liquid metal fast breeder reactors, Sodium fast reactors, Transients (Dynamics), Breeder reactors, Fast neutron reactors, Feedback
Proceedings Papers

Numerical Simulation of Flow Regime Transition From Slug to Wavy Flow in Helically Coiled Tubes

Zhaoxu Li, Hongye Zhu
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T10A009, June 26–30, 2016
Paper No: ICONE24-60235
https://doi.org/10.1115/ICONE24-60235
View Paper titled, Numerical Simulation of Flow Regime Transition From Slug to Wavy Flow in Helically Coiled Tubes
Open the PDF for Numerical Simulation of Flow Regime Transition From Slug to Wavy Flow in Helically Coiled Tubes in another window
Topics: Computer simulation, Flow (Dynamics), Slug flows, Centrifugal force, Two-phase flow, Heat transfer, Pressurized water reactors, Computational fluid dynamics, Boilers, Breeder reactors
Proceedings Papers

RELAP5-3D Analysis of EBR-II Shutdown Heat Removal Test SHRT-17

Domenico De Luca, Alessandro Petruzzi, Marco Cherubini, Valeria Parrinello
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A046, June 26–30, 2016
Paper No: ICONE24-60629
https://doi.org/10.1115/ICONE24-60629
View Paper titled, RELAP5-3D Analysis of EBR-II Shutdown Heat Removal Test SHRT-17
Open the PDF for RELAP5-3D Analysis of EBR-II Shutdown Heat Removal Test SHRT-17 in another window
Topics: Heat, Flow (Dynamics), Pumps, Steady state, Transients (Dynamics), Coolants, Metals, Sodium fast reactors, Temperature, Transient analysis
Proceedings Papers

Fuel-Cell and Electrolysis By-Product D2O Improves Third Way to Mitigate CO2

William Ernest Schenewerk
Proc. ASME. NUCLRF2015, ASME 2015 Nuclear Forum, V001T01A001, June 28–July 2, 2015
Paper No: NUCLRF2015-49061
https://doi.org/10.1115/NUCLRF2015-49061
View Paper titled, Fuel-Cell and Electrolysis By-Product D2O Improves Third Way to Mitigate CO2
Open the PDF for Fuel-Cell and Electrolysis By-Product D2O Improves Third Way to Mitigate CO2 in another window
Topics: Carbon dioxide, Electrolysis, Fuel cells, Nuclear power, Hydrogen, Seawater, Water, Breeder reactors, Condensed matter, Uranium
Proceedings Papers

Influence of Hydrodynamic Interaction on Jet Breakup and Fragmentation Behavior

Shimpei Saito, Yutaka Abe, Akiko Kaneko, Yuzuru Iwasawa, Eiji Matsuo, Ken-ichi Ebihara, Hiroshi Sakaba, Kazuya Koyama, Hideki Nariai
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A005, July 7–11, 2014
Paper No: ICONE22-30028
https://doi.org/10.1115/ICONE22-30028
View Paper titled, Influence of Hydrodynamic Interaction on Jet Breakup and Fragmentation Behavior
Open the PDF for Influence of Hydrodynamic Interaction on Jet Breakup and Fragmentation Behavior in another window
Topics: Accidents, Air entrainment, Breeder reactors, Coolants, Cooling, Fluids, Fluorescence, Heat, Lasers, Nozzles
Proceedings Papers

Numerical Investigation on Thermal Striping Phenomena in a T-Junction Piping System

Masaaki Tanaka, Yasuhiro Miyake
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, V004T10A028, July 7–11, 2014
Paper No: ICONE22-30683
https://doi.org/10.1115/ICONE22-30683
View Paper titled, Numerical Investigation on Thermal Striping Phenomena in a T-Junction Piping System
Open the PDF for Numerical Investigation on Thermal Striping Phenomena in a T-Junction Piping System in another window
Topics: Junctions, Piping systems, Computer simulation, Eddies (Fluid dynamics), Pipes, Vortices, Wakes, Cycles, Fatigue, Temperature
Proceedings Papers

Design of 500 MWe Metal Fuel Demonstration Fast Reactor

Chellapandi Perumal, V. Balasubramaniyan, P. Puthiyavinayagam, Raghupathy Sundararajan, Madhusoodanan Kanakkil, P. Selvaraj, P. R. Vasudeva Rao
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A020, July 7–11, 2014
Paper No: ICONE22-30727
https://doi.org/10.1115/ICONE22-30727
View Paper titled, Design of 500 MWe Metal Fuel Demonstration Fast Reactor
Open the PDF for Design of 500 MWe Metal Fuel Demonstration Fast Reactor in another window
Topics: Design, Fast neutron reactors, Fuels, Metals, Breeder reactors, Heavy water reactors, Uranium, Nuclear power, Construction, Engineering prototypes
Proceedings Papers

Design Improvement Studies for Future SFR

Rajan Babu V., V. Balasubramaniyan, Raghupathy Sundararajan, P. Puthiyavinayagam, Chellapandi Perumal
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A021, July 7–11, 2014
Paper No: ICONE22-30742
https://doi.org/10.1115/ICONE22-30742
View Paper titled, Design Improvement Studies for Future SFR
Open the PDF for Design Improvement Studies for Future SFR in another window
Topics: Design, Sodium fast reactors, Manufacturing, Sodium, Construction, Heat, Vessels, Breeder reactors, Circuits, Dimensions
Proceedings Papers

3D FEA Elastoplastic Structural Analysis of Hypothetically Cracked Monju FBR Core Support Structures

Daniel Garcia-Rodriguez, Shinichiro Matsubara
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T03A014, July 7–11, 2014
Paper No: ICONE22-30382
https://doi.org/10.1115/ICONE22-30382
View Paper titled, 3D FEA Elastoplastic Structural Analysis of Hypothetically Cracked Monju FBR Core Support Structures
Open the PDF for 3D FEA Elastoplastic Structural Analysis of Hypothetically Cracked Monju FBR Core Support Structures in another window
Topics: Finite element analysis, Structural analysis, Shells, Accidents, Breeder reactors, Design, Earthquakes, Fracture (Materials), Reliability, Solid models
Proceedings Papers

Effect of Physical Properties on Gas Entrainment Rate From Free Surface by Vortex (2nd Report)

Yasuo Koizumi, Naosuke Ohte, Hideki Kamide, Shuji Ohno, Kei Ito
Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A041, July 7–11, 2014
Paper No: ICONE22-30959
https://doi.org/10.1115/ICONE22-30959
View Paper titled, Effect of Physical Properties on Gas Entrainment Rate From Free Surface by Vortex (2nd Report)
Open the PDF for Effect of Physical Properties on Gas Entrainment Rate From Free Surface by Vortex (2nd Report) in another window
Topics: Vortices, Bubbles, Flow (Dynamics), Pipes, Sodium, Surface tension, Viscosity, Water, Breeder reactors, Coolants
Proceedings Papers

SKYTHIA: A Universal Multi-Phase Flow Analyzer

Nikolay Ivanov Kolev
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, V004T10A051, July 7–11, 2014
Paper No: ICONE22-31285
https://doi.org/10.1115/ICONE22-31285
View Paper titled, SKYTHIA: A Universal Multi-Phase Flow Analyzer
Open the PDF for SKYTHIA: A Universal Multi-Phase Flow Analyzer in another window
Topics: Multiphase flow, Water, Equilibrium (Physics), Fluids, Flow (Dynamics), Pipes, Simulation, Boilers, Piping systems, Steam