nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
A comparison of empirical potential models for the simulation of dislocations in uranium dioxide
|
Murphy, Samuel T. |
|
2014 |
72 |
C |
p. 27-32 6 p. |
artikel |
2 |
An experimental device to study the revaporisation behaviour of fission product deposits under severe accident conditions
|
Knebel, K. |
|
2014 |
72 |
C |
p. 77-82 6 p. |
artikel |
3 |
Characterization of uranium neodymium oxide microspheres synthesized by internal gelation
|
Schreinemachers, C. |
|
2014 |
72 |
C |
p. 17-21 5 p. |
artikel |
4 |
Conditioning of minor actinides in lanthanum monazite ceramics: A surrogate study with Europium
|
Brandt, F. |
|
2014 |
72 |
C |
p. 140-143 4 p. |
artikel |
5 |
Crystallographic comparison of zirconium and molybdenum dioxide-based pyrochlores
|
Kasano, Takayuki |
|
2014 |
72 |
C |
p. 134-139 6 p. |
artikel |
6 |
Design, development and utilisation of a tomography station for γ-ray emission and transmission analyses of light water reactor spent fuel rods
|
Caruso, S. |
|
2014 |
72 |
C |
p. 49-54 6 p. |
artikel |
7 |
Development and demonstration of innovative partitioning processes (i-SANEX and 1-cycle SANEX) for actinide partitioning
|
Modolo, G. |
|
2014 |
72 |
C |
p. 107-114 8 p. |
artikel |
8 |
Dissolution of uranium mixed oxides: The role of oxygen vacancies vs the redox reactions
|
Tocino, Florent |
|
2014 |
72 |
C |
p. 101-106 6 p. |
artikel |
9 |
Editorial Board
|
|
|
2014 |
72 |
C |
p. IFC- 1 p. |
artikel |
10 |
Electron energy loss spectroscopy investigations through nano-ablated actinide dioxide samples
|
Degueldre, Claude |
|
2014 |
72 |
C |
p. 96-100 5 p. |
artikel |
11 |
Existence of a miscibility gap in uranium neodymium oxide materials used as nuclear fuels simulants
|
Dottavio, G. |
|
2014 |
72 |
C |
p. 22-26 5 p. |
artikel |
12 |
Fission product release from accident tested irradiated High Temperature Reactor fuel pebbles
|
Seeger, O. |
|
2014 |
72 |
C |
p. 72-76 5 p. |
artikel |
13 |
Investigation of the influence of off-stoichiometry on the radiation damage evolution in uranium dioxide
|
Ngayam-Happy, Raoul |
|
2014 |
72 |
C |
p. 38-43 6 p. |
artikel |
14 |
Laser melting of nano-crystalline uranium dioxide
|
Cappia, F. |
|
2014 |
72 |
C |
p. 11-16 6 p. |
artikel |
15 |
Modelling actinide redistribution in mixed oxide fuel for sodium fast reactors
|
Di Marcello, Valentino |
|
2014 |
72 |
C |
p. 83-90 8 p. |
artikel |
16 |
Neutron radiography and tomography applied to fuel degradation during ramp tests and loss of coolant accident tests in a research reactor
|
Jenssen, Håkon Kristian |
|
2014 |
72 |
C |
p. 55-62 8 p. |
artikel |
17 |
On-line deformation measurements of nuclear fuel rod cladding using speckle interferometry
|
Fabert, M. |
|
2014 |
72 |
C |
p. 44-48 5 p. |
artikel |
18 |
Peculiarities of fuel cycle with advanced composite fuel for thermal reactors
|
Savchenko, A.M. |
|
2014 |
72 |
C |
p. 119-125 7 p. |
artikel |
19 |
Raman and infrared spectroscopy of monazite-type ceramics used for nuclear waste conditioning
|
Heuser, J. |
|
2014 |
72 |
C |
p. 149-155 7 p. |
artikel |
20 |
Scanning acoustic microscope for mechanical characterization and density estimation of irradiated nuclear fuel
|
Laux, D. |
|
2014 |
72 |
C |
p. 63-66 4 p. |
artikel |
21 |
Studies on thermal and mechanical properties of monazite-type ceramics for the conditioning of minor actinides
|
Arinicheva, Y. |
|
2014 |
72 |
C |
p. 144-148 5 p. |
artikel |
22 |
Swelling due to the partition of soluble fission products between the grey phase and uranium dioxide
|
Cooper, M.W.D. |
|
2014 |
72 |
C |
p. 33-37 5 p. |
artikel |
23 |
Synthesis and dissolution kinetics of zirconia based ceramics
|
Finkeldei, S. |
|
2014 |
72 |
C |
p. 130-133 4 p. |
artikel |
24 |
The first Symposium on the Scientific Basis of the Nuclear Fuel Cycle Symposium E @ EMRS 13 Editorial note
|
Degueldre, Claude |
|
2014 |
72 |
C |
p. 1-2 2 p. |
artikel |
25 |
The Scientific Basis of the Nuclear Fuel Cycle
|
Degueldre, Claude |
|
2014 |
72 |
C |
p. 3-4 2 p. |
artikel |
26 |
Thorium fuel production and results from beginning of life irradiation
|
Drera, Saleem S. |
|
2014 |
72 |
C |
p. 5-10 6 p. |
artikel |
27 |
Utilization of dual-column focused ion beam and scanning electron microscope for three dimensional characterization of high burn-up mixed oxide fuel
|
Teague, Melissa |
|
2014 |
72 |
C |
p. 67-71 5 p. |
artikel |
28 |
Validation of analytical methods for nuclear spent fuel reprocessing
|
Rivier, C. |
|
2014 |
72 |
C |
p. 115-118 4 p. |
artikel |
29 |
Variants of the perspective closed fuel cycle, based on Regenerated Mixture – Technology, combining use of thermal and fast reactors
|
Alekseev, P.N. |
|
2014 |
72 |
C |
p. 126-129 4 p. |
artikel |
30 |
X-ray absorption in plutonium uranium mixed oxide fuel: Thorium characterization
|
Cozzo, C. |
|
2014 |
72 |
C |
p. 91-95 5 p. |
artikel |