Digitale Bibliotheek
Sluiten Bladeren door artikelen uit een tijdschrift
 
Zoeken naar met titel:
ABCDEFGHIJKLMNOPQRSTUVWXYZ

     Tijdschrift beschrijving
       Alle jaargangen van het bijbehorende tijdschrift
         Alle afleveringen van het bijbehorende jaargang
                                       Alle artikelen van de bijbehorende aflevering
 
                             50 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A comparison of regularization operators for noisy gamma-ray tomographic reconstruction Araújo, Bruna G.M.
 2015
 83 C p. 1-7
7 p.
 artikel
2 A comparison of traditional and hybrid radiation detector dead-time models and detector behavior Yousaf, M.
 2015
 83 C p. 177-185
9 p.
 artikel
3 A cross-entropy method applied to the In-core fuel management optimization of a Pressurized Water Reactor de Moura Meneses, Anderson Alvarenga
 2015
 83 C p. 326-335
10 p.
 artikel
4 Advanced passive design of small modular reactor cooled by heavy liquid metal natural circulation Shin, Yong-Hoon
 2015
 83 C p. 433-442
10 p.
 artikel
5 A feasibility study on low-enriched uranium fuel for nuclear thermal rockets – I: Reactivity potential Venneri, Paolo F.
 2015
 83 C p. 406-418
13 p.
 artikel
6 A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics Zanetti, Matteo
 2015
 83 C p. 82-98
17 p.
 artikel
7 A passive decay heat removal system for the lead cooled fast reactor demonstrator “Alfred” Damiani, Lorenzo
 2015
 83 C p. 294-304
11 p.
 artikel
8 A 232Th closed fuel cycle utilizing both a thermal and hybrid nuclear systems Perez-Gamboa, M.
 2015
 83 C p. 135-143
9 p.
 artikel
9 Balancing exploration and exploitation in differential evolution via variable scaling factors: An application to practical problems Sacco, W.F.
 2015
 83 C p. 365-373
9 p.
 artikel
10 Behaviors of passive safety systems under a Feed Water Line Break LOCA on a Generation III+ Boiling Water Reactor Yang, Jun
 2015
 83 C p. 35-42
8 p.
 artikel
11 Cement-waste interactions: Hardening self-compacting mortar exposed to gamma radiation Craeye, B.
 2015
 83 C p. 212-219
8 p.
 artikel
12 Core neutronics characterization of the GFR2400 Gas Cooled Fast Reactor Perkó, Zoltán
 2015
 83 C p. 460-481
22 p.
 artikel
13 Corrigendum to “Fuzzy logic-based safety design for high performance air compressors” [Prog. Nuclear Energy 80C (2014) 136–150] Deol, Harsh
 2015
 83 C p. 497-
1 p.
 artikel
14 Development of barium borosilicate glasses for radiation shielding materials using rice husk ash as a silica source Ruengsri, S.
 2015
 83 C p. 99-104
6 p.
 artikel
15 Dissolution kinetics of Indian PHWR natural UO2 fuel pellets in nitric acid – Effect of initial acidity and temperature Desigan, N.
 2015
 83 C p. 52-58
7 p.
 artikel
16 Drift-flux model for rod bundle geometry Ozaki, Tetsuhiro
 2015
 83 C p. 229-247
19 p.
 artikel
17 Editorial Board 2015
 83 C p. IFC-
1 p.
 artikel
18 Effect of burnup on the neutronic parameters of ITU TRIGA Mark II research reactor Türkmen, Mehmet
 2015
 83 C p. 26-34
9 p.
 artikel
19 Effect of mix parameters and hydrogen loading on neutron radiation shielding characteristics of latex modified concrete mixes Malkapur, Santhosh M.
 2015
 83 C p. 8-12
5 p.
 artikel
20 Experimental study of natural circulation instability with void reactivity feedback during startup transients for a BWR-type SMR Shi, Shanbin
 2015
 83 C p. 73-81
9 p.
 artikel
21 Experimental study of neutronic parameters in Tehran research reactor mixed-core Lashkari, A.
 2015
 83 C p. 398-405
8 p.
 artikel
22 Heat transfer and friction in nonuniform wall roughness lattice Xiao, Hongguang
 2015
 83 C p. 43-51
9 p.
 artikel
23 Innovative model of annular fuel design for lead-cooled fast reactors Rowinski, Marcin Karol
 2015
 83 C p. 270-282
13 p.
 artikel
24 Investigation of severe accident scenario of PWR response to LOCA along with SBO Hu, Liang
 2015
 83 C p. 159-166
8 p.
 artikel
25 MCNP design of thermal and epithermal neutron beam for BNCT at the Isfahan MNSR Monshizadeh, M.
 2015
 83 C p. 427-432
6 p.
 artikel
26 Modeling of AP1000 and simulation of 10-inch cold leg small break LOCA using the CESAR thermal-hydraulic module of ASTEC Di Giuli, M.
 2015
 83 C p. 387-397
11 p.
 artikel
27 Modeling primary and secondary coolant of a nuclear power plant system with a unique framework (MCUF) Pack, J.
 2015
 83 C p. 197-211
15 p.
 artikel
28 Modifying the neutron diffusion equation using spatial fractional operators and developed diffusion coefficients Maleki Moghaddam, Nader
 2015
 83 C p. 59-72
14 p.
 artikel
29 Natural circulation characteristics analysis of a small modular natural circulation lead–bismuth eutectic cooled fast reactor Zhao, Pengcheng
 2015
 83 C p. 220-228
9 p.
 artikel
30 Neutronics evaluation of a super-deep-burn with TRU Fully Ceramic Microencapsulated (FCM) fuel in CANDU Hartanto, Donny
 2015
 83 C p. 261-269
9 p.
 artikel
31 Numerical simulation of single bubble condensation in subcooled flow using OpenFOAM Zeng, Qingyun
 2015
 83 C p. 336-346
11 p.
 artikel
32 Out-containment mitigation of gaseous iodine by alkaline spray in severe accident situation Younus, Irfan
 2015
 83 C p. 167-176
10 p.
 artikel
33 Performance upgrades to the MCNP6 burnup capability for large scale depletion calculations Fensin, M.L.
 2015
 83 C p. 186-190
5 p.
 artikel
34 Preliminary tests of particle image velocimetry for the upper plenum of a scaled model of a very high temperature gas cooled reactor McVay, Kyle L.
 2015
 83 C p. 305-317
13 p.
 artikel
35 PSO with Dynamic Topology and Random Keys method applied to Nuclear Reactor Reload Câmara Augusto, João Pedro da Silveira
 2015
 83 C p. 191-196
6 p.
 artikel
36 Recent advances on the use of reprocessed fuels and combined thorium fuel cycles in HTR systems Fortini, A.
 2015
 83 C p. 482-496
15 p.
 artikel
37 SARCS cross section library generator: Part two: Fast and quasi transients evaluations Hadad, K.
 2015
 83 C p. 347-355
9 p.
 artikel
38 SCWR transient safety analysis code SCAC-CSR1000 Liu, Liang
 2015
 83 C p. 318-325
8 p.
 artikel
39 Study of minor actinides effect on kinetic parameters and reactivity coefficients in an accelerator driven system Luo, Run
 2015
 83 C p. 419-426
8 p.
 artikel
40 Study of the γ-U(Mo) phase decomposition for atomised and ground powders Champion, G.
 2015
 83 C p. 248-255
8 p.
 artikel
41 Sustainability of the Chinese nuclear expansion: The role of ADS to close the nuclear fuel cycle Fiori, F.
 2015
 83 C p. 123-134
12 p.
 artikel
42 The theoretical study of the deuterium enrichment of H-D gas mixture in continuous-type thermal-diffusion columns Ho, Chii-Dong
 2015
 83 C p. 152-158
7 p.
 artikel
43 The use of zirconium hydride blankets in a minor actinide/thorium burner sodium-cooled reactor for void coefficient control with particular reference to UK's plutonium disposition problem Arias, Francisco J.
 2015
 83 C p. 256-260
5 p.
 artikel
44 The VHTR and GFR and their use in innovative symbiotic fuel cycles Chersola, Davide
 2015
 83 C p. 443-459
17 p.
 artikel
45 Transient analysis of an FHR coupled to a helium Brayton power cycle Chen, Minghui
 2015
 83 C p. 283-293
11 p.
 artikel
46 Transient behaviors of heavy water reflector system during postulated initiating events (PIEs) Kim, Kyung-O.
 2015
 83 C p. 144-151
8 p.
 artikel
47 Two-phase mixture simulation of Al2O3/water nanofluid heat transfer in a non-uniform heat addition test section Abbassi, Yasser
 2015
 83 C p. 356-364
9 p.
 artikel
48 Ultraslow wave nuclear burning of uranium–plutonium fissile medium on epithermal neutrons Rusov, V.D.
 2015
 83 C p. 105-122
18 p.
 artikel
49 Uranium utilization with thorium blanket in Pebble Bed Fluoride salt-cooled high temperature reactor Zhu, Guifeng
 2015
 83 C p. 374-386
13 p.
 artikel
50 Verification of the evaluated fission product yields data from the neutron induced fission of 235U, 238U and 239Pu based on the delayed neutron characteristics Gremyachkin, D.E.
 2015
 83 C p. 13-25
13 p.
 artikel
                             50 gevonden resultaten
 
 Koninklijke Bibliotheek - Nationale Bibliotheek van Nederland