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Nuclear Fuel Cycle, Spent Fuel and Radwaste Management
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Proceedings Papers

Development of Enriched Borated Aluminum Alloy for Basket Material of Cask for Spent Nuclear Fuel

Katsura Kajihara, Yasuhiro Aruga, Jun Shimojo, Hiroaki Taniuchi, Tsutomu Takeda, Masatosi Sasaki
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 235-242, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22025
https://doi.org/10.1115/ICONE10-22025
View Paper titled, Development of Enriched Borated Aluminum Alloy for Basket Material of Cask for Spent Nuclear Fuel
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Topics: Aluminum alloys, Spent nuclear fuels
Proceedings Papers

Collection of Spent Solid Radioactive Sources

Marie-France Robbe, Sandrine Matton, Fabrice Lamadie, Pascal Devenelle, Eric Vincon, Laurent Laloubere
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 433-443, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22642
https://doi.org/10.1115/ICONE10-22642
View Paper titled, Collection of Spent Solid Radioactive Sources
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Topics: Nuclear fuel cycle, Radioactive wastes
Proceedings Papers

Thermal Analysis of the One-Stage Melting Converter and Related Equipment for Vitrification of High-Level Radioactive Wastes

L. S. Pioro, I. L. Pioro, K. E. P’yanykh
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 331-338, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22397
https://doi.org/10.1115/ICONE10-22397
View Paper titled, Thermal Analysis of the One-Stage Melting Converter and Related Equipment for Vitrification of High-Level Radioactive Wastes
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Topics: Melting, Radioactive wastes, Thermal analysis, Vitrification
Proceedings Papers

Effect of Loading Pattern on Thermal and Shielding Performance of a Spent Fuel Cask

Mikal A. McKinnon, Judith M. Cuta, Urban P. Jenquin
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 243-250, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22041
https://doi.org/10.1115/ICONE10-22041
View Paper titled, Effect of Loading Pattern on Thermal and Shielding Performance of a Spent Fuel Cask
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Topics: Cladding systems (Building), Design, Fuels, Heat, Licensing, Spent fuel storage, Spent nuclear fuels, Storage, Stress, Temperature
Proceedings Papers

Possibility of Different Fuel Cycles Usage in GT-MHR

N. Kodochigov, Yu. Sukharev, E. Marova, N. Ponomarev-Stepnoy, E. Glushkov, P. Fomichenko, C. Ellis
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 339-342, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22404
https://doi.org/10.1115/ICONE10-22404
View Paper titled, Possibility of Different Fuel Cycles Usage in GT-MHR
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Topics: Cycles, Fuels, Design, Rods, Stress, Accounting, Dimensions, Isotopes, Nuclear fuel cycle, Power density
Proceedings Papers

Receipt and Storage Issues at the TMI-2 Irradiated Fuel Storage Installation

Allan B. Christensen, Kenneth Custer, Rick Gardner, James Kaylor, James Stalnaker
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 445-455, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22649
https://doi.org/10.1115/ICONE10-22649
View Paper titled, Receipt and Storage Issues at the TMI-2 Irradiated Fuel Storage Installation
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Topics: Spent nuclear fuels, Storage, Drainage, Drying, Welding, Containers, Fuels, Hydrogen, Licensing, Nuclear fuels
Proceedings Papers

The Effect of the Hydrogen to Heavy Metal Ratio (H/HM) on Reactivity and Discharge Isotopics of Homogeneous Thoria-Urania Fuel

Kevan D. Weaver, J. Stephen Herring
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 251-257, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22070
https://doi.org/10.1115/ICONE10-22070
View Paper titled, The Effect of the Hydrogen to Heavy Metal Ratio (H/HM) on Reactivity and Discharge Isotopics of Homogeneous Thoria-Urania Fuel
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Topics: Fuels, Heavy metals, Hydrogen, Uranium, Neutrons, Density, Coolants, Hardening, Manufacturing, Nuclear fission
Proceedings Papers

Restructuring the Uranium Mining Industry in Romania: Actual Situation and Prospects

P. D. Georgescu, S. T. Petrescu, T. F. Iuhas
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 457-462, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22657
https://doi.org/10.1115/ICONE10-22657
View Paper titled, Restructuring the Uranium Mining Industry in Romania: Actual Situation and Prospects
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Topics: Uranium mining, Uranium, Construction, Energetics, Mining, Nuclear power stations, Prospecting, Water
Proceedings Papers

Examination of Spent PWR Fuel Rods After 15 Years in Dry Storage

R. E. Einziger, H. C. Tsai, M. C. Billone, B. A. Hilton
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 351-358, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22456
https://doi.org/10.1115/ICONE10-22456
View Paper titled, Examination of Spent PWR Fuel Rods After 15 Years in Dry Storage
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Topics: Fuel rods, Fuels, Pressurized water reactors, Storage
Proceedings Papers

Engineered Barriers in the Waste Isolation Pilot Plant

Shankar Ghose
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 259-271, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22087
https://doi.org/10.1115/ICONE10-22087
View Paper titled, Engineered Barriers in the Waste Isolation Pilot Plant
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Topics: Fluids
Proceedings Papers

Development of Thermal Analysis Capability of Dry Storage Cask for Spend Fuel Interim Storage

Fu-Kuang Ko, Thomas K. S. Liang, Chung-Yu Yang
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 463-471, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22665
https://doi.org/10.1115/ICONE10-22665
View Paper titled, Development of Thermal Analysis Capability of Dry Storage Cask for Spend Fuel Interim Storage
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Topics: Fuels, Storage, Thermal analysis, Heat transfer, Radiation (Physics), Heat conduction, Spent nuclear fuels, Cladding systems (Building), Concretes, Convection
Proceedings Papers

Radial Power Profile of MOX and LEU Fuel Pellet Versus Burnup

Gray S. Chang, Robert C. Pedersen
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 359-367, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22483
https://doi.org/10.1115/ICONE10-22483
View Paper titled, Radial Power Profile of MOX and LEU Fuel Pellet Versus Burnup
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Topics: Fuels, Light water reactors, Nuclear fission, Performance evaluation, Spent nuclear fuels, Weapons
Proceedings Papers

Gross Gamma Dose Rate Measurements for TRIGA Spent Nuclear Fuel Burnup Validation

P. L. Winston, J. W. Sterbentz
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 273-280, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22138
https://doi.org/10.1115/ICONE10-22138
View Paper titled, Gross Gamma Dose Rate Measurements for TRIGA Spent Nuclear Fuel Burnup Validation
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Topics: Spent nuclear fuels
Proceedings Papers

Completion of Experimental Breeder Reactor-II Sodium Processing at Argonne National Laboratory

Mary D. McDermott, Charles D. Griffin, Daniel K. Baird, Carl E. Baily, John A. Michelbacher, Kenneth E. Rosenberg, S. Paul Henslee
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 369-376, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22485
https://doi.org/10.1115/ICONE10-22485
View Paper titled, Completion of Experimental Breeder Reactor-II Sodium Processing at Argonne National Laboratory
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Topics: Sodium
Proceedings Papers

Cyclic Mode of Transmutation of Minor Actinides in Heavy-Water Reactor

Aleksander S. Gerasimov, Gennady V. Kiselev, Lidia A. Myrtsymova, Tamara S. Zaritskaya
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 473-476, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22668
https://doi.org/10.1115/ICONE10-22668
View Paper titled, Cyclic Mode of Transmutation of Minor Actinides in Heavy-Water Reactor
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Topics: Water, Thermal energy, Cycles, Equilibrium (Physics), Nuclides, Spent nuclear fuels, Stress
Proceedings Papers

Modeling of MOX Fuel Pellet-Clad Interaction Using ABAQUS

Richard G. Ambrosek, Robert C. Pedersen, Amanda Maple
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 281-286, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22142
https://doi.org/10.1115/ICONE10-22142
View Paper titled, Modeling of MOX Fuel Pellet-Clad Interaction Using ABAQUS
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Topics: Fuels, Modeling, Irradiation (Radiation exposure), Displacement, Pins (Engineering), Temperature
Proceedings Papers

Development of the Concrete Cask Horizontal Transfer System

Mikio Sakai, Hiroaki Fujiwara, Tadatsugu Sakaya, Akira Sakai
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 377-382, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22495
https://doi.org/10.1115/ICONE10-22495
View Paper titled, Development of the Concrete Cask Horizontal Transfer System
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Topics: Concretes, Storage, Heat, Rails, Temperature, Spent nuclear fuels, Stress, Thermal analysis, Transportation systems, Accidents
Proceedings Papers

Renovation of Chemical Processing Facility for Development of Advanced Fast Reactor Fuel Cycle System in JNC

Atsushi Aoshima, Shigehiko Miyachi, Takashi Suganuma, Shinichi Nemoto
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 383-387, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22512
https://doi.org/10.1115/ICONE10-22512
View Paper titled, Renovation of Chemical Processing Facility for Development of Advanced Fast Reactor Fuel Cycle System in JNC
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Topics: Building renovation, Fast neutron reactors, Nuclear fuel cycle
Proceedings Papers

Radiotoxicity of Actinides During Transmutation in Final Stage of Atomic Power

Aleksander S. Gerasimov, Boris R. Bergelson, Lidia A. Myrtsymova, Georgy V. Tikhomirov
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 477-480, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22669
https://doi.org/10.1115/ICONE10-22669
View Paper titled, Radiotoxicity of Actinides During Transmutation in Final Stage of Atomic Power
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Topics: Nuclear power, Neutron flux, Nuclides
Proceedings Papers

Mixed Reload Design Using MOX and UOX Fuel Assemblies

J. Ramo´n Rami´rez Sa´nchez, R. T. Perry
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 287-290, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22143
https://doi.org/10.1115/ICONE10-22143
View Paper titled, Mixed Reload Design Using MOX and UOX Fuel Assemblies
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Topics: Design, Fuels, Cycles, Stress, Boiling water reactors, Gadolinium, Manufacturing, Conceptual design, Neutrons, Rods