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Proceedings Papers

Criticality Safety Analysis of Fuel Storage Under Fuel Assembly Dropping Accident

Mingliang Dai, Pengtao Fu, Jun Zhao
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A013, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90509
https://doi.org/10.1115/ICONE29-90509
View Paper titled, Criticality Safety Analysis of Fuel Storage Under Fuel Assembly Dropping Accident
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Topics: Accidents, Fuel storage, Fuels, Manufacturing, Safety
Proceedings Papers

Criticality Study of Spent Fuel Storage Rack of Ship-Based Small Modular Reactor

Yaoxin Ye, Jun Zhao, Yunfei Xu
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A037, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93407
https://doi.org/10.1115/ICONE29-93407
View Paper titled, Criticality Study of Spent Fuel Storage Rack of Ship-Based Small Modular Reactor
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Topics: Ships, Small modular reactors, Spent fuel storage, Storage, Accidents, Boron, Deformation, Fuel storage, Fuels, Accounting
Proceedings Papers

Optimization of Fuel Storage in Spent Fuel Pool

Xinyu Wang, Richard Cable Kurwitz, Zhijian Zhang
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A006, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81084
https://doi.org/10.1115/ICONE26-81084
View Paper titled, Optimization of Fuel Storage in Spent Fuel Pool
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Topics: Fuel storage, Optimization, Spent nuclear fuels, Algorithms, Manufacturing, Fuels, Genetic algorithms, Nuclear power stations, Vacuum
Proceedings Papers

Analysis on Impact of Fuel Thermal Conductivity Degradation (TCD) on Large Break Loss of Coolant Accidents of CAP1000

Wang Weiwei, Lu Lu
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A024, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66283
https://doi.org/10.1115/ICONE25-66283
View Paper titled, Analysis on Impact of Fuel Thermal Conductivity Degradation (TCD) on Large Break Loss of Coolant Accidents of CAP1000
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Topics: Accidents, Coolants, Fuels, Thermal conductivity, Temperature, Cladding systems (Building), Fuel storage, Nuclear fuels, Nuclear power stations, Sensitivity analysis
Proceedings Papers

Development of Probabilistic Risk Assessment Methodology of Decay Heat Removal Function Against Combination Hazards of Strong Wind and Rainfall for Sodium-Cooled Fast Reactors

Hidemasa Yamano, Hiroyuki Nishino, Kenichi Kurisaka
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T14A005, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66059
https://doi.org/10.1115/ICONE25-66059
View Paper titled, Development of Probabilistic Risk Assessment Methodology of Decay Heat Removal Function Against Combination Hazards of Strong Wind and Rainfall for Sodium-Cooled Fast Reactors
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Topics: Hazards, Heat, Probabilistic risk assessment, Sodium fast reactors, Wind, Failure, Missiles, Cooling systems, Drops, Wind velocity
Proceedings Papers

Qualification Requirements Design for Neutron Absorber Plate for Spent Fuel Racks in Domestic Nuclear Power Plants

You Shi, Dong Ning, Yi-zhong Yang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A026, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66256
https://doi.org/10.1115/ICONE25-66256
View Paper titled, Qualification Requirements Design for Neutron Absorber Plate for Spent Fuel Racks in Domestic Nuclear Power Plants
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Topics: Design, Neutrons, Nuclear power stations, Spent nuclear fuels, China, Density, Manufacturing, Spent fuel storage, Testing, Aluminum
Proceedings Papers

Safety Assessment of Fuel Storage Ponds Following Cooling Faults

Jonathan Webb, Charles Bridgford
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, V002T07A006, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60267
https://doi.org/10.1115/ICONE24-60267
View Paper titled, Safety Assessment of Fuel Storage Ponds Following Cooling Faults
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Topics: Cooling, Fuel storage, Safety, Water, Temperature, Containment, Cooling systems, Spent nuclear fuels, Concretes, Cracking (Materials)
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30742
https://doi.org/10.1115/ICONE22-30742
View Paper titled, Design Improvement Studies for Future SFR
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Topics: Design, Sodium fast reactors, Manufacturing, Sodium, Construction, Heat, Vessels, Breeder reactors, Circuits, Dimensions
Proceedings Papers

Numerical Simulation of a Completely Passive Spent Fuel Pool: Lessons Learned

Elia Merzari, Yousry Gohar
Proc. ASME. ICONE20-POWER2012, Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Controls; Fuels and Combustion, Materials Handling, Emissions; Advanced Energy Systems and Renewables (Wind, Solar, Geothermal); Performance Testing and Performance Test Codes, 553-561, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54797
https://doi.org/10.1115/ICONE20-POWER2012-54797
View Paper titled, Numerical Simulation of a Completely Passive Spent Fuel Pool: Lessons Learned
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Topics: Computer simulation, Spent nuclear fuels, Simulation, Natural convection, Computational fluid dynamics, Design, Heat, Cooling, Fuel storage, Fuels
Proceedings Papers

Plant Dynamics Evaluation of a Monju Ex-Vessel Fuel Storage System During a Station Blackout

Takero Mori, Masutake Sotsu, Kei Honda, Satoshi Suzuki, Hiroaki Ohira
Proc. ASME. ICONE20-POWER2012, Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries, 615-625, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54854
https://doi.org/10.1115/ICONE20-POWER2012-54854
View Paper titled, Plant Dynamics Evaluation of a Monju Ex-Vessel Fuel Storage System During a Station Blackout
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Topics: Dynamics (Mechanics), Fuel storage, Vessels, Sodium, Cooling, Cooling systems, Heat, Temperature, Coolers, Flow (Dynamics)
Proceedings Papers

RBMK Fuel Rod Modelling and Investigation of Process During Operation Cycle

Tadas Kaliatka, Ausˇra Marao, Renatas Karalevicˇius, Eugenijus Usˇpuras
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 739-745, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29952
https://doi.org/10.1115/ICONE18-29952
View Paper titled, RBMK Fuel Rod Modelling and Investigation of Process During Operation Cycle
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Topics: Cycles, Fuel rods, Modeling, Cladding systems (Building), Fuels, Spent nuclear fuels, Deformation, Fuel storage, Residual stresses, Safety
Proceedings Papers

Fortum Participation in IAEA Benchmark for KKNPP7 RHR Piping Response NCO 2007 Event

Pentti Varpasuo, Jukka Ka¨hko¨nen
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 435-441, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29229
https://doi.org/10.1115/ICONE18-29229
View Paper titled, Fortum Participation in IAEA Benchmark for KKNPP7 RHR Piping Response NCO 2007 Event
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Topics: Pipes, Simulation, Heat, Earthquakes, Buckling, Computer simulation, Piping systems, Sloshing, Databases, Displacement measurement
Proceedings Papers

Transmutation Efficiency of Plutonium and Minor Actinides in PHWR

Nineta Balas (Ghizdeanu), Petre Ghitescu
Proc. ASME. ICONE16, Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 111-119, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48570
https://doi.org/10.1115/ICONE16-48570
View Paper titled, Transmutation Efficiency of Plutonium and Minor Actinides in PHWR
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Topics: Heavy water reactors, Fuels, Spent nuclear fuels, Engineering simulation, Fuel storage, Irradiation (Radiation exposure), Isotopes, Nuclear power stations, Pressurized water reactors, Simulation
Proceedings Papers

A Comparative Evaluation of Licensing Requirements for Dry Storage of Spent Nuclear Fuel in the United States, Germany, Canada and the Russian Federation

Edward Wonder, David S. Duncan, Eric A. Howden
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 2, 643-650, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49551
https://doi.org/10.1115/ICONE12-49551
View Paper titled, A Comparative Evaluation of Licensing Requirements for Dry Storage of Spent Nuclear Fuel in the United States, Germany, Canada and the Russian Federation
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Topics: Licensing, Spent nuclear fuels, Storage, Regulations, Spent fuel storage, Fuel storage, Fuels, Transportation systems
Proceedings Papers

The Development of Mobile Melt-Dilute Technology for the Treatment of Former Soviet Union Research Reactor Fuel

D. A. Sell, E. A. Howden, K. J. Allen, K. Marsden, B. R. Westphal, H. B. Peacock, N. C. Iyer, D. L. Fisher, T. M. Adams, R. L. Sindelar
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 3, 245-251, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49550
https://doi.org/10.1115/ICONE12-49550
View Paper titled, The Development of Mobile Melt-Dilute Technology for the Treatment of Former Soviet Union Research Reactor Fuel
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Topics: Nuclear fuels, Weapons, Spent nuclear fuels, Storage, Uranium, Conceptual design, Design, Engineering prototypes, Fuel storage, Furnaces
Proceedings Papers

Axial Burnup Profile Influence on Criticality Safety of WWER Spent Fuel

Surik Bznuni, Armen Amirjanyan, Shahen Poghosyan
Proc. ASME. ICONE14, Volume 5: Safety and Security; Low Level Waste Management, Decontamination and Decommissioning; Nuclear Industry Forum, 131-134, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89252
https://doi.org/10.1115/ICONE14-89252
View Paper titled, Axial Burnup Profile Influence on Criticality Safety of WWER Spent Fuel
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Topics: Safety, Spent nuclear fuels, Spent fuel storage, Accidents, Fuel storage, Fuels, Neutrons, Nuclear fission, Nuclear power stations, Radiation (Physics)