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Proceedings Papers

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

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

Paper No: ICONE2020-16633

DOI: https://doi.org/10.1115/ICONE2020-16633

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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

Yong Mann Song, Jong Yeob Jung, Sunil Nijhawan

Paper No: ICONE2020-16634

DOI: https://doi.org/10.1115/ICONE2020-16634

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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

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

Paper No: ICONE2020-16647

DOI: https://doi.org/10.1115/ICONE2020-16647

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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

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

Paper No: ICONE2020-16514

DOI: https://doi.org/10.1115/ICONE2020-16514

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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

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

Paper No: ICONE25-66205

DOI: https://doi.org/10.1115/ICONE25-66205

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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

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

Paper No: ICONE24-60689

DOI: https://doi.org/10.1115/ICONE24-60689

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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

Paul Ponomaryov, Yifeng Zhou, Cristina-Maria Mazza, Igor Pioro

Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A021, June 26–30, 2016

Paper No: ICONE24-60353

DOI: https://doi.org/10.1115/ICONE24-60353

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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

Yifeng Zhou, Paul Ponomaryov, Cristina Mazza, Igor Pioro

Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A028, June 26–30, 2016

Paper No: ICONE24-60442

DOI: https://doi.org/10.1115/ICONE24-60442

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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

Sunil Nijhawan

Proc. ASME. NUCLRF2015, ASME 2015 Nuclear Forum, V001T02A002, June 28–July 2, 2015

Paper No: NUCLRF2015-49574

DOI: https://doi.org/10.1115/NUCLRF2015-49574

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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

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

Paper No: ICONE22-30812

DOI: https://doi.org/10.1115/ICONE22-30812

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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

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

DOI: https://doi.org/10.1115/ICONE22-30727

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Topics: Design, Fast neutron reactors, Fuels, Metals, Breeder reactors, Heavy water reactors, Uranium, Nuclear power, Construction, Engineering prototypes

Proceedings Papers

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

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

Paper No: ICONE21-16103

DOI: https://doi.org/10.1115/ICONE21-16103

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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

Motonari Haraguchi, Tateki Nakamura, Hideo Yoda, Takeshi Kudo, Shigeki Senoo

Paper No: ICONE21-16600

DOI: https://doi.org/10.1115/ICONE21-16600

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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

The Research of PHWR Reactor Feeder Flow Measurement

Xin Sheng

Paper No: ICONE21-16468

DOI: https://doi.org/10.1115/ICONE21-16468

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Topics: Flow measurement, Heavy water reactors, Fuels, Heat, Boilers, Cooling, Design, Errors, Flow (Dynamics), Nuclear fission

Proceedings Papers

The Study of Qinshan III PHWR Thermosyphoning Capability

Xin Sheng

Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A025, July 29–August 2, 2013

Paper No: ICONE21-15280

DOI: https://doi.org/10.1115/ICONE21-15280

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Topics: Heavy water reactors, Cooling, Nuclear power stations, Accidents, Heat sinks, Safety, Temperature, Boilers, Design, Fuels

Proceedings Papers

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

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

Paper No: ICONE20-POWER2012-54066

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54066

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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

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

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

Paper No: ICONE20-POWER2012-54387

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54387

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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

Enhanced CANDU 6: An Upgraded Reactor Product With Optimal Fuel Cycle Capability

Jerry Hopwood, Ian J. Hastings, Michael Soulard

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 369-373, May 17–21, 2010

Paper No: ICONE18-30343

DOI: https://doi.org/10.1115/ICONE18-30343

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Topics: Control rooms, Cycles, Design, Feedback, Fuels, Heavy water reactors, Maintenance, Neutron flux, Nuclear fuel cycle, Nuclear power

Proceedings Papers

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

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

Paper No: ICONE18-29320

DOI: https://doi.org/10.1115/ICONE18-29320

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Topics: Simulation, Safety, Accidents, Heavy water reactors, Coolants, Engineering standards, Light water reactors, Nuclear power, Computers, Heat

Proceedings Papers

LOCA Event Tree Analysis for Qinshan Phase III CANDU-6 PHWR NPP

Limin Zheng

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 251-259, May 17–21, 2010

Paper No: ICONE18-29746

DOI: https://doi.org/10.1115/ICONE18-29746

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Topics: Heavy water reactors, Nuclear power stations

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NARROW

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

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

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

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

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

Challenges in Multi-Unit CANDU Reactor Severe Accident Mitigation Strategies

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

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

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

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

Design of 500 MWe Metal Fuel Demonstration Fast Reactor

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

Nuclear Steam Turbine With 60 inch Last Stage Blade

The Research of PHWR Reactor Feeder Flow Measurement

The Study of Qinshan III PHWR Thermosyphoning Capability

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

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

Enhanced CANDU 6: An Upgraded Reactor Product With Optimal Fuel Cycle Capability

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

LOCA Event Tree Analysis for Qinshan Phase III CANDU-6 PHWR NPP

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