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                             27 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Atom probe study of radiation induced grain boundary segregation/depletion in a Fe-12%Cr alloy Hu, Rong
2012
57 C p. 14-19
6 p.
artikel
2 Cladding for high performance fuel Hallstadius, Lars
2012
57 C p. 71-76
6 p.
artikel
3 Corrosion behavior of Alloy 625 in supercritical water environments Chang, Kai-Hsiang
2012
57 C p. 20-31
12 p.
artikel
4 Corrosion of ZrO2 treated type 304 stainless steels in high temperature pure water with various amounts of hydrogen peroxide Yeh, Tsung-Kuang
2012
57 C p. 62-70
9 p.
artikel
5 Depth profile of chemical states of alloying elements in oxide layer of Zr-based alloys Sakamoto, K.
2012
57 C p. 101-105
5 p.
artikel
6 Deuterium diffusion in LiOH–water-corroded oxide layer of zirconium alloys Une, K.
2012
57 C p. 93-100
8 p.
artikel
7 Editorial Board 2012
57 C p. IFC-
1 p.
artikel
8 Editorial Note on Symposium V @ EMRS 11 2012
57 C p. 1-
1 p.
artikel
9 Fabrication of oxidic uranium-neodymium microspheres by internal gelation Daniels, H.
2012
57 C p. 106-110
5 p.
artikel
10 Fabrication of SiC–SiC composites for fuel cladding in advanced reactor designs Deck, C.P.
2012
57 C p. 38-45
8 p.
artikel
11 High temperature annealing of Xe implanted ZrC0.95O0.05 investigated by RBS, TEM and PAS-DBS Gutierrez, G.
2012
57 C p. 57-61
5 p.
artikel
12 Innovative production of nuclear fuel by microwave internal gelation: Heat transfer model of falling droplets Cabanes-Sempere, M.
2012
57 C p. 111-116
6 p.
artikel
13 In situ TEM observation of interactions between gliding dislocations and prismatic loops in Zr-ion irradiated zirconium alloys Onimus, F.
2012
57 C p. 77-85
9 p.
artikel
14 Investigation of irradiated uranium-plutonium mixed oxide fuel by synchrotron based micro X-ray diffraction Mieszczynski, C.
2012
57 C p. 130-137
8 p.
artikel
15 MACROS benchmark calculations and analysis of fission gas release in MOX with high content of plutonium Lemehov, Sergei E.
2012
57 C p. 117-124
8 p.
artikel
16 Microstructural evolutions of three-dimensional carbon–carbon composite materials irradiated by carbon ions at elevated temperatures Tsai, Shuo-Cheng
2012
57 C p. 32-37
6 p.
artikel
17 Physical properties and leaching behaviour of spent fuel BISO coated particles Bukaemskiy, A.
2012
57 C p. 161-164
4 p.
artikel
18 Precipitation in long term thermally aged high copper, high nickel model RPV steel welds Styman, P.D.
2012
57 C p. 86-92
7 p.
artikel
19 Preparation and characterization of synthetic Th0.5U0.5SiO4 uranothorite Costin, D.T.
2012
57 C p. 155-160
6 p.
artikel
20 Protected plutonium production at fast breeder reactor blanket – Chemical analysis of uranium-238 samples irradiated in the experimental fast reactor Joyo Ohnishi, Takashi
2012
57 C p. 125-129
5 p.
artikel
21 Quantifying helium distribution in dual-ion beam irradiated SiCf/SiC composites by electron energy loss spectroscopy Chen, K.F.
2012
57 C p. 46-51
6 p.
artikel
22 Structural irradiation damage and recovery in nanometric silicon carbide Gosset, D.
2012
57 C p. 52-56
5 p.
artikel
23 Structure of UMo4O14 oxide Zakharov, N.D.
2012
57 C p. 150-154
5 p.
artikel
24 TEM characterization of precipitates in EUROFER 97 Klimenkov, M.
2012
57 C p. 8-13
6 p.
artikel
25 Thermal conductivity of highly neutron-irradiated beryllium in nuclear fusion reactors Chakin, V.
2012
57 C p. 2-7
6 p.
artikel
26 Xenon migration in UO2: A SIMS study Marchand, B.
2012
57 C p. 145-149
5 p.
artikel
27 Zirconium alloys matrix as innovative material for composite fuel Savchenko, A.M.
2012
57 C p. 138-144
7 p.
artikel
                             27 gevonden resultaten
 
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