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 |