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CONFERENCE
6/16/2013 - 6/19/2013
The 7th International conference on Physical and Numerical Simulation of Materials Processing
5/16/2013 - 5/19/2013
2nd International Congress on Advanced Materials
4/13/2013 - 4/14/2013
2013 2nd lnternational Conference on lntclligent Materials, Applied Mechanics and Design Science (IMAMD 2013)
more...
Articles by keyword: «
Nuclear Fuel
»
16 papers on 2 pages:
1
[2]
[next]
An Alternative Method to Produce U
3
O
8
Powder for MTR Fuel Elements
Published in:
Advanced Powder Technology II
(p32)
Application of Combustion Synthesis to the Production of Actinide Bearing Nitride Ceramic Nuclear Fuels
Published in:
PRICM 6
(p1749)
Axial Fission Gas Transport in Nuclear Fuel Rods
Published in:
Diffusion in Solids and Liquids IV
(p262)
Characteristics of U and U-7wt%Mo Polycrystalline Foils Cast by Alternative Fabrication Method
Published in:
Advances in Nanomaterials and Processing
(p1473)
Creep Tests Research on a New Zirconium Alloy for Nuclear Fuel Cladding Tubes
Published in:
New Trends in Mechatronics and Materials Engineering
(p47)
Effect of Mixed Powder Homogeneity on the UO
2
-Gd
2
O
3
Nuclear Fuel Sintering Behavior
Published in:
Advanced Powder Technology II
(p60)
Fabrication of Cermet Nuclear Fuels Designed for the Transmutation of Transuranic Isotopes
Published in:
PRICM 6
(p1733)
Fabrication of Monolithic UAl
2
Pellet for High-Density Nuclear Fuel
Published in:
Advanced Materials and Processing
(p925)
Fabrication of U
3
Si
2
Powder for Fuels Used in IEA-R1 Nuclear Research Reactor
Published in:
Advanced Powder Technology VI
(p194)
Modelling Fission Gas Bubble Distribution in UO
2
Published in:
Diffusion in Materials - DIMAT 2011
(p209)
Modelling of Stable Fission Gases Diffusion in UO
2
Nuclear Fuel
Published in:
Diffusion in Solids and Liquids III
(p693)
Nano-Scale Crystallite Size Measurement of Attrition Milled Oxide Nuclear Fuel Powders by Neutron Diffraction Line Broadening
Published in:
Metastable, Mechanically Alloyed and Nanocrystalline Materials 2002
(p415)
Restructuring of Nuclear Oxide Fuel under High Burnup Irradiation
Published in:
11th International Ceramics Congress
(p1952)
Technological Aspects Concerning the Production Procedures of UO
2
-Gd
2
O
3
Nuclear Fuel
Published in:
Advanced Powder Technology VI
(p673)
Thermal Interdiffusion Products of U-10Mo in Al Matrix
Published in:
Advanced Powder Technology VII
(p69)
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