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Journal of Nuclear Materials
Title
Publication Date
Language
Citations
Long term corrosion on T91 and AISI1 316L steel in flowing lead alloy and corrosion protection barrier development: Experiments and models
2011/08/01
English
140
Assessment of ODS-14%Cr ferritic alloy for high temperature applications
2004/08/01
English
139
Present status of vanadium alloys for fusion applications
2014/12/01
English
139
Microstructural development in cubic silicon carbide during irradiation at elevated temperatures
2006/06/01
English
139
TEM and HRTEM study of oxide particles in an Al-alloyed high-Cr oxide dispersion strengthened steel with Zr addition
2014/01/01
English
139
Plasma operation with an all metal first-wall: Comparison of an ITER-like wall with a carbon wall in JET
2013/07/01
English
138
Oxidation behavior of ferritic–martensitic and ODS steels in supercritical water
2012/05/01
English
138
Oxygen and uranium diffusion in uranium dioxide (a review)
1969/04/01
English
138
Dynamic observations of heavy-ion damage in Fe and Fe–Cr alloys
2009/05/01
English
138
Development status of CLAM steel for fusion application
2014/12/01
English
137
Plasma-wall interaction and plasma behaviour in the non-boronised all tungsten ASDEX Upgrade
2009/06/01
English
137
The rate of hydrogen release out of clean metallic surfaces
1978/09/01
English
137
Oxidation of ferritic–martensitic alloys T91, HCM12A and HT-9 in supercritical water
2007/09/01
English
136
Ferritic-martensitic steels for fission and fusion applications
2019/09/01
English
136
The distribution of intragranular fission gas bubbles in UO2 during irradiation
1971/02/01
English
136
Plasma detachment from divertor targets and limiters
1995/04/01
English
136
Effects of ELMs on ITER divertor armour materials
2007/06/01
English
135
A density functional theory assessment of the clustering behaviour of He and H in tungsten
2009/04/01
English
135
Point defect sink strengths and void-swelling
1976/06/01
English
135
Status and key issues of reduced activation ferritic/martensitic steels as the structural material for a DEMO blanket
2011/10/01
English
135
Photon interaction and energy absorption in glass: A transparent gamma ray shield
2009/09/01
English
135
Barium borosilicate glass – a potential matrix for immobilization of sulfate bearing high-level radioactive liquid waste
2006/11/01
English
134
Correlation between chemical composition and size of very small oxide particles in the MA957 ODS ferritic alloy
2009/02/01
English
134
Diffusion coefficient of hydrogen in alpha zirconium, Zircaloy-2 and Zircaloy-4
1972/06/01
English
134
Characterisation of radiation-damage microstructures by TEM
1994/10/01
English
134
Vanadium-base alloys for fusion reactor applications — a review
1985/10/01
English
133
Composition and structure of fission product precipitates in irradiated oxide fuels: Correlation with phase studies in the Mo-Ru-Rh-Pd and BaO-UO2-ZrO2-MoO2 Systems
1985/02/01
English
133
Immobilization of tetravalent actinides in phosphate ceramics
2006/06/01
English
133
The configuration of atomic defects as determined from scattering studies
1978/02/01
English
133
Helium bubble formation in ultrafine and nanocrystalline tungsten under different extreme conditions
2015/03/01
English
133
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