Volumes | International Conference on Nuclear Engineering | American Society of Mechanical Engineers Digital Collection

ASME 2015 Nuclear Forum collocated with the ASME 2015 Power Conference, the ASME 2015 9th International Conference on Energy Sustainability, and the ASME 2015 13th International Conference on Fuel Cell Science, Engineering and Technology

June 28–July 2, 2015

San Diego, California, USA

Conference Sponsors:

ISBN:

978-0-7918-5686-4

In This Volume

Advanced and Small Modular Reactors (4)
Engineering for Safety, Beyond Design Basis Events, and Non-Proliferation (2)
Materials, Structures and Components (4)
Thermal Hydraulics and Computational Fluid Dynamics (2)

ASME 2015 Nuclear Forum

Advanced and Small Modular Reactors

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

William Ernest Schenewerk

ICONE 2015; V001T01A001https://doi.org/10.1115/NUCLRF2015-49061

Abstract

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

PDF

Topics: Carbon dioxide , Electrolysis , Fuel cells , Nuclear power , Hydrogen , Seawater , Water , Breeder reactors , Condensed matter , Uranium

Exergy Analysis for Small Modular Reactor Hybrid Energy System

Lauren Boldon, Piyush Sabharwall, Li (Emily) Liu

ICONE 2015; V001T01A002https://doi.org/10.1115/NUCLRF2015-49083

Abstract

View Articletitled, Exergy Analysis for Small Modular Reactor Hybrid Energy System

PDF

Topics: Exergy analysis , Small modular reactors , Thermoeconomics , Energy / power systems , Exergy , System efficiency , Carbon , Complex systems , Economics , Heat

Lessons Learned and Improvements in ANL Plant Dynamics Code Simulation of Experimental S-CO₂ Loops

Anton Moisseytsev, James J. Sienicki

ICONE 2015; V001T01A003https://doi.org/10.1115/NUCLRF2015-49182

Abstract

View Articletitled, Lessons Learned and Improvements in ANL Plant Dynamics Code Simulation of Experimental S-CO2 Loops

PDF

Topics: Dynamics (Mechanics) , Simulation , Supercritical carbon dioxide , Modeling , Cycles

A Supercritical CO₂ Brayton Cycle Power Converter for a Sodium-Cooled Fast Reactor Small Modular Reactor

James J. Sienicki, Anton Moisseytsev, Lubomir Krajtl

ICONE 2015; V001T01A004https://doi.org/10.1115/NUCLRF2015-49185

Abstract

View Articletitled, A Supercritical CO2 Brayton Cycle Power Converter for a Sodium-Cooled Fast Reactor Small Modular Reactor

PDF

Topics: Brayton cycle , Power converters , Small modular reactors , Sodium fast reactors , Supercritical carbon dioxide , Sodium , Cycles , Temperature , Energy conversion , Heat

Engineering for Safety, Beyond Design Basis Events, and Non-Proliferation

High Temperature Intrinsically Safe Nuclear Reactor

Robin J. McDaniel

ICONE 2015; V001T02A001https://doi.org/10.1115/NUCLRF2015-49422

Abstract

View Articletitled, High Temperature Intrinsically Safe Nuclear Reactor

PDF

Topics: High temperature , Nuclear reactors , Design , Coolants , Flow (Dynamics) , Fast neutron reactors , Renewable energy , Safety , Small modular reactors , Accidents

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

Sunil Nijhawan

ICONE 2015; V001T02A002https://doi.org/10.1115/NUCLRF2015-49574

Abstract

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

PDF

Topics: Accidents , Design , Heavy water reactors , Risk reduction , Fuels , Containment , Hydrogen , Nuclear fission , Pressure , Alternating current (Electricity)

Materials, Structures and Components

Effects of the Shape of the Foil Corners on the Irradiation Performance of U10Mo Alloy Based Monolithic Mini-Plates

Hakan Ozaltun, Pavel Medvedev

ICONE 2015; V001T03A001https://doi.org/10.1115/NUCLRF2015-49284

Abstract

View Articletitled, Effects of the Shape of the Foil Corners on the Irradiation Performance of U10Mo Alloy Based Monolithic Mini-Plates

PDF

Topics: Alloys , Corners (Structural elements) , Irradiation (Radiation exposure) , Plates (structures) , Shapes , Fuels , Manufacturing , Stress , Engineering simulation , Simulation

Impact of Mechanical Constraints on the Irradiation Performance of U10Mo Monolithic Mini-Plates

Walid Mohamed, Hee Seok Roh, Gerard Hofman, Pavel G. Medvedev

ICONE 2015; V001T03A002https://doi.org/10.1115/NUCLRF2015-49455

Abstract

View Articletitled, Impact of Mechanical Constraints on the Irradiation Performance of U10Mo Monolithic Mini-Plates

PDF

Topics: Degrees of freedom , Irradiation (Radiation exposure) , Plates (structures) , Fuels , Stress , Cladding systems (Building) , Uranium , Displacement , Alloys , Density

Effects of the Foil Centering on the Irradiation Performance of U10Mo Alloy Based Monolithic Mini-Plates

Jill Wright, Hakan Ozaltun

ICONE 2015; V001T03A003https://doi.org/10.1115/NUCLRF2015-49462

Abstract

View Articletitled, Effects of the Foil Centering on the Irradiation Performance of U10Mo Alloy Based Monolithic Mini-Plates

PDF

Topics: Alloys , Irradiation (Radiation exposure) , Plates (structures) , Fuels , Cladding systems (Building) , Cooling , Engineering simulation , Manufacturing , Simulation , Warping

Fission Products Distribution in TRISO Coated Fuel Particles Irradiated to 3.22 X 10²¹ n/cm² Fast Fluence at 1092°C

Haiming Wen, Isabella J. Van Rooyen, Connie M. Hill, Tammy L. Trowbridge, Ben D. Coryell

ICONE 2015; V001T03A004https://doi.org/10.1115/NUCLRF2015-49695

Abstract

View Articletitled, Fission Products Distribution in TRISO Coated Fuel Particles Irradiated to 3.22 X 1021 n/cm2 Fast Fluence at 1092°C

PDF

Topics: Fluence (Radiation measurement) , Fuels , Nuclear fission , Particulate matter , Silicon , Transmission electron microscopy , Carbon , Coating processes , Coatings , Electrons

Thermal Hydraulics and Computational Fluid Dynamics

The Effects of Subcooling on Quenching of a Vertical Brass Cylinder With Heating Power

Yuan-Hong Ho, Ming-Xi Ho, Chin Pan

ICONE 2015; V001T04A001https://doi.org/10.1115/NUCLRF2015-49307

Abstract

View Articletitled, The Effects of Subcooling on Quenching of a Vertical Brass Cylinder With Heating Power

PDF

Topics: Brass (Metal) , Cylinders , Heating , Quenching (Metalworking) , Subcooling , Film boiling , Coolants , Heat , Nuclear power stations , Water

Sensitivity Evaluation of the Daily Thermal Predictions of the AGR-2 Experiment in the Advanced Test Reactor

Grant L. Hawkes, James W. Sterbentz, Binh T. Pham

ICONE 2015; V001T04A002https://doi.org/10.1115/NUCLRF2015-49698

Abstract

View Articletitled, Sensitivity Evaluation of the Daily Thermal Predictions of the AGR-2 Experiment in the Advanced Test Reactor

PDF

Topics: Finite element analysis , Fluence (Radiation measurement) , Fuels , Graphite , Heat , Neutrons , Particulate matter , Stainless steel , Temperature , Thermal conductivity

All Years

Advanced and Small Modular Reactors

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

Exergy Analysis for Small Modular Reactor Hybrid Energy System

Lessons Learned and Improvements in ANL Plant Dynamics Code Simulation of Experimental S-CO₂ Loops

A Supercritical CO₂ Brayton Cycle Power Converter for a Sodium-Cooled Fast Reactor Small Modular Reactor

Engineering for Safety, Beyond Design Basis Events, and Non-Proliferation

High Temperature Intrinsically Safe Nuclear Reactor

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

Materials, Structures and Components

Effects of the Shape of the Foil Corners on the Irradiation Performance of U10Mo Alloy Based Monolithic Mini-Plates

Impact of Mechanical Constraints on the Irradiation Performance of U10Mo Monolithic Mini-Plates

Effects of the Foil Centering on the Irradiation Performance of U10Mo Alloy Based Monolithic Mini-Plates

Fission Products Distribution in TRISO Coated Fuel Particles Irradiated to 3.22 X 10²¹ n/cm² Fast Fluence at 1092°C

Thermal Hydraulics and Computational Fluid Dynamics

The Effects of Subcooling on Quenching of a Vertical Brass Cylinder With Heating Power

Sensitivity Evaluation of the Daily Thermal Predictions of the AGR-2 Experiment in the Advanced Test Reactor

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Proceedings Papers

Advanced and Small Modular Reactors

Engineering for Safety, Beyond Design Basis Events, and Non-Proliferation

Materials, Structures and Components

Thermal Hydraulics and Computational Fluid Dynamics

Email alerts

Most Read Proceedings Papers in ICONE

ASME Journals

ASME Conference Proceedings

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Resources

Opportunities

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