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                             30 gevonden resultaten
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
                             30 gevonden resultaten
 
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