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Proceedings Papers

Total Monte Carlo Uncertainty Analysis of VVER-440 Spent Nuclear Fuel in LWR and HWR Reactor Environment

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Martin Lovecký, Jiří Závorka, Tomáš Kořínek, Radek Škoda
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A050, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136014
https://doi.org/10.1115/ICONE31-136014
View Paper titled, Total Monte Carlo Uncertainty Analysis of VVER-440 Spent Nuclear Fuel in LWR and HWR Reactor Environment
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Topics: Heat, Heavy water reactors, Light water reactors, Spent nuclear fuels, Uncertainty analysis
Proceedings Papers

Simulation of Severe Accident Progression Using ROSHNI: A New Integrated Simulation Code for PHWR Severe Accidents

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Sunil Nijhawan, YongMann Song
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, V001T01A014, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16633
https://doi.org/10.1115/ICONE2020-16633
View Paper titled, Simulation of Severe Accident Progression Using ROSHNI: A New Integrated Simulation Code for PHWR Severe Accidents
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Topics: Accidents, Heavy water reactors, Simulation, Fuels, Design, Modeling, Vessels, Damage, Failure, Fluids
Proceedings Papers

FUELPOOL: A Computer Program to Model CANDU Spent Fuel Pool Severe Accident Progression and Consequences

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Yong Mann Song, Jong Yeob Jung, Sunil Nijhawan
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, V001T01A015, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16634
https://doi.org/10.1115/ICONE2020-16634
View Paper titled, FUELPOOL: A Computer Program to Model CANDU Spent Fuel Pool Severe Accident Progression and Consequences
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Topics: Accidents, Computer software, Spent nuclear fuels, Fuels, Fluids, Heavy water reactors, Radiation (Physics), Stainless steel, Steel, Water
Proceedings Papers

Experimental Investigations on Thermal Stratification in a Large Pool of Water With Immersed Isolation Condenser

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Sunil Kumar, P. K. Vijayan, R. B. Grover, U. Kannan, Harekrishna Yadav, A. Agrawal
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A033, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16647
https://doi.org/10.1115/ICONE2020-16647
View Paper titled, Experimental Investigations on Thermal Stratification in a Large Pool of Water With Immersed Isolation Condenser
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Topics: Condensers (steam plant), Thermal stratification, Water, Heat, Heat exchangers, Boiling, Density, Gravity (Force), Heavy water reactors, Hot water
Proceedings Papers

Neutronics and Thermal Hydraulics Coupled 3-D Calculation of Pressure-Tube Deformation

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Eunhyun Ryu, Hangyu Joo, Seungyul Yoo, Jongyub Jung
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A027, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16514
https://doi.org/10.1115/ICONE2020-16514
View Paper titled, Neutronics and Thermal Hydraulics Coupled 3-D Calculation of Pressure-Tube Deformation
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Topics: Deformation, Heavy water reactors, Pressure, Thermal hydraulics
Proceedings Papers

CANDU PHWR Feeder Pipe FAC Mitigation Design Modification and Validation During Operation

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Tang Jiongran, Shang Junmin, Yang Yue, Yuan Jianzhong
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T01A008, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66205
https://doi.org/10.1115/ICONE25-66205
View Paper titled, CANDU PHWR Feeder Pipe FAC Mitigation Design Modification and Validation During Operation
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Topics: Design, Heavy water reactors, Pipes, Corrosion, Flow (Dynamics), Heat, In-service inspection, Nuclear power, Nuclear power stations, Service life (Equipment)
Proceedings Papers

Challenges in Multi-Unit CANDU Reactor Severe Accident Mitigation Strategies

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Sunil Nijhawan
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, V004T13A013, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60689
https://doi.org/10.1115/ICONE24-60689
View Paper titled, Challenges in Multi-Unit CANDU Reactor Severe Accident Mitigation Strategies
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Topics: Accidents, Design, Boilers, Pressure, Containment, Heat, Safety, Accident management, Analytical methods, Leakage
Proceedings Papers

Modifications of Generic Pressurized-Water Reactor Units to Increase Cycle Efficiency

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Paul Ponomaryov, Yifeng Zhou, Cristina-Maria Mazza, Igor Pioro
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A021, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60353
https://doi.org/10.1115/ICONE24-60353
View Paper titled, Modifications of Generic Pressurized-Water Reactor Units to Increase Cycle Efficiency
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Topics: Cycles, Water, Turbines, Heavy water reactors, Thermal efficiency, Pressurized water reactors, Boiling water reactors, Molten salt reactors, Nuclear power stations, Steam
Proceedings Papers

Investigation of Thermal Efficiency of Generic Pressure-Channel Reactors With Steam Reheat

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Yifeng Zhou, Paul Ponomaryov, Cristina Mazza, Igor Pioro
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A028, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60442
https://doi.org/10.1115/ICONE24-60442
View Paper titled, Investigation of Thermal Efficiency of Generic Pressure-Channel Reactors With Steam Reheat
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Topics: Pressure, Steam, Thermal efficiency, Water, Nuclear power stations, Nuclear reactors, Design, Heavy water reactors, Boiling, Boiling water reactors
Proceedings Papers

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

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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

Two-Way Coupling Between the Reactor Dynamics Code DYN3D and the Fuel Performance Code TRANSURANUS at Assembly Level

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L. Holt, U. Rohde, M. Seidl, A. Schubert, P. Van Uffelen, R. Macián-Juan
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A052, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30812
https://doi.org/10.1115/ICONE22-30812
View Paper titled, Two-Way Coupling Between the Reactor Dynamics Code DYN3D and the Fuel Performance Code TRANSURANUS at Assembly Level
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Topics: Dynamics (Mechanics), Fuels, Manufacturing, Thermal hydraulics, Transients (Dynamics), Modeling, Temperature, Heat transfer, Pressurized water reactors, Accidents
Proceedings Papers

Design of 500 MWe Metal Fuel Demonstration Fast Reactor

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30727
https://doi.org/10.1115/ICONE22-30727
View Paper titled, Design of 500 MWe Metal Fuel Demonstration Fast Reactor
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Topics: Design, Fast neutron reactors, Fuels, Metals, Breeder reactors, Heavy water reactors, Uranium, Nuclear power, Construction, Engineering prototypes
Proceedings Papers

The Study of Qinshan III PHWR Thermosyphoning Capability

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Xin Sheng
Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A025, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15280
https://doi.org/10.1115/ICONE21-15280
View Paper titled, The Study of Qinshan III PHWR Thermosyphoning Capability
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Topics: Heavy water reactors, Cooling, Nuclear power stations, Accidents, Heat sinks, Safety, Temperature, Boilers, Design, Fuels
Proceedings Papers

The Research of PHWR Reactor Feeder Flow Measurement

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Xin Sheng
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, V001T01A037, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16468
https://doi.org/10.1115/ICONE21-16468
View Paper titled, The Research of PHWR Reactor Feeder Flow Measurement
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Topics: Flow measurement, Heavy water reactors, Fuels, Heat, Boilers, Cooling, Design, Errors, Flow (Dynamics), Nuclear fission
Proceedings Papers

Optimization of CANDU6 Heat Transport System Inventory Control During On-Power Refueling

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Zhigang Wu, Chuanqing Lin, Yang Liu
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, V001T01A027, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16103
https://doi.org/10.1115/ICONE21-16103
View Paper titled, Optimization of CANDU6 Heat Transport System Inventory Control During On-Power Refueling
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Topics: Condensers (steam plant), Cutting, Design, Feedforward control, Flow (Dynamics), Heat, Heavy water reactors, Leakage, Machinery, Nuclear power stations
Proceedings Papers

Nuclear Steam Turbine With 60 inch Last Stage Blade

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Motonari Haraguchi, Tateki Nakamura, Hideo Yoda, Takeshi Kudo, Shigeki Senoo
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, V001T01A042, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16600
https://doi.org/10.1115/ICONE21-16600
View Paper titled, Nuclear Steam Turbine With 60 inch Last Stage Blade
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Topics: Blades, Steam turbines, Steam, Water, Boiling water reactors, Countermeasures, Heavy water reactors, Nuclear power, Pressure, Pressurized water reactors
Proceedings Papers

Improved Regulatory Oversight and Immediate Retrofits for Operating Pressurized Heavy Water Reactors for Beyond Design Basis Accidents

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Sunil Nijhawan
Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 673-686, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54387
https://doi.org/10.1115/ICONE20-POWER2012-54387
View Paper titled, Improved Regulatory Oversight and Immediate Retrofits for Operating Pressurized Heavy Water Reactors for Beyond Design Basis Accidents
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Topics: Accidents, Design, Heavy water reactors, Containment, Damage, Failure, Fukushima nuclear disaster, Japan, 2011, Nuclear reactors, Public utilities, Safety
Proceedings Papers

Identification of Limiting Case Between DBA and SBDBA (CL Break Area Sensitivity): A New Model for the Boron Injection System

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Raul Gonzalez, Alessandro Petruzzi, Francesco D’Auria, Oscar Mazzantini
Proc. ASME. ICONE20-POWER2012, Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries, 37-43, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54066
https://doi.org/10.1115/ICONE20-POWER2012-54066
View Paper titled, Identification of Limiting Case Between DBA and SBDBA (CL Break Area Sensitivity): A New Model for the Boron Injection System
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Topics: Boron, Boundary-value problems, Cladding systems (Building), Computational fluid dynamics, Construction, Control systems, Heavy water reactors, Neutrons, Nuclear power stations, Rods
Proceedings Papers

Simulation of B9401 Test in the RD-14M Experimental Facility With CATHARE2

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Mirea Mladin, Daniela Mladin
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 333-342, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29320
https://doi.org/10.1115/ICONE18-29320
View Paper titled, Simulation of B9401 Test in the RD-14M Experimental Facility With CATHARE2
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Topics: Simulation, Safety, Accidents, Heavy water reactors, Coolants, Engineering standards, Light water reactors, Nuclear power, Computers, Heat
Proceedings Papers

Scenarios for the Transmutation of Actinides in CANDU Reactors

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Bronwyn Hyland, Brian Gihm
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 533-543, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30123
https://doi.org/10.1115/ICONE18-30123
View Paper titled, Scenarios for the Transmutation of Actinides in CANDU Reactors
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Topics: Design, Fuels, Heat, Heavy water reactors, Isotopes, Manufacturing, Neutron flux, Nuclear environmental management, Nuclear fuels, Separation (Technology)