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                             26 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A cycle-specific cross-section update for real-time simulation of VVER-1000 core Georgieva, Emiliya L.
2014
74 C p. 222-231
10 p.
artikel
2 A self-adaptive quantum PBIL method for the nuclear reload optimization Henrique da Silva, Márcio
2014
74 C p. 103-109
7 p.
artikel
3 Assessment of passive safety system performance under gravity driven cooling system drain line break accident Lim, J.
2014
74 C p. 136-142
7 p.
artikel
4 A theoretical analysis about the mechanism of the effect of rolling motion on single-phase flow resistance in rectangular duct Xing, Dianchuan
2014
74 C p. 53-60
8 p.
artikel
5 Databases of interfacial area concentration in gas–liquid two-phase flow Lin, Chih-Hung
2014
74 C p. 91-102
12 p.
artikel
6 Dynamic analysis of AP1000 shield building for various elevations and shapes of air intakes considering FSI effects subjected to seismic loading Zhao, Chunfeng
2014
74 C p. 44-52
9 p.
artikel
7 Editorial Board 2014
74 C p. IFC-
1 p.
artikel
8 Effects of some parameters on mass-transfer efficiency of a ϕ20 mm annular centrifugal contactor for nuclear solvent extraction processes Zhao, Mingming
2014
74 C p. 154-159
6 p.
artikel
9 Estimation of radionuclide transport to reactor containment building under unprotected severe accident scenario in SFR Pradeep, Arjun
2014
74 C p. 120-128
9 p.
artikel
10 Experimental study and numerical optimization on a vane-type separator for bubble separation in TMSR Cai, Baowei
2014
74 C p. 1-13
13 p.
artikel
11 Experimental study of head loss through an LOCA-generated fibrous debris bed deposited on a sump strainer for Generic Safety Issue 191 Lee, Saya
2014
74 C p. 166-175
10 p.
artikel
12 Final characterization of the first critical configuration for the TRIGA Mark II reactor of the University of Pavia using the Monte Carlo code MCNP Alloni, D.
2014
74 C p. 129-135
7 p.
artikel
13 Full scope thermal-neutronic analysis of LOFA in a WWER-1000 reactor core by coupling PARCS v2.7 and COBRA-EN Noori-Kalkhoran, Omid
2014
74 C p. 193-200
8 p.
artikel
14 Measurement of neutronic safety parameters of the 3 MW TRIGA Mark-II research reactor Salam, M.A.
2014
74 C p. 160-165
6 p.
artikel
15 Modeling and system analysis of fuel cycles for nuclear power sustainability (III): An integrated evaluation Gao, Fanxing
2014
74 C p. 79-90
12 p.
artikel
16 Numerical study of non-uniform magnetic fields effects on subcooled nanofluid flow boiling Aminfar, Habib
2014
74 C p. 232-241
10 p.
artikel
17 Numerical study on the heat transfer characteristics of LIVE-L4 melt pool with a partial solidification process Zhang, Y.P.
2014
74 C p. 213-221
9 p.
artikel
18 Parametric study on maximum transportable distance and cost for thermal energy transportation using various coolants Yoon, Su-Jong
2014
74 C p. 110-119
10 p.
artikel
19 Path-planning research in radioactive environment based on particle swarm algorithm Liu, Yong-kuo
2014
74 C p. 184-192
9 p.
artikel
20 Radioactivity release from the Fukushima accident and its consequences: A review Koo, Yang-Hyun
2014
74 C p. 61-70
10 p.
artikel
21 Review of droplet entrainment in annular flow: Interfacial waves and onset of entrainment Berna, C.
2014
74 C p. 14-43
30 p.
artikel
22 Scaling analysis of AP1000 ADS-4 entrainment and depressurization Sun, D.C.
2014
74 C p. 71-78
8 p.
artikel
23 Short-term and long-term analysis of WWER-1000 containment parameters in a large break LOCA Noori-Kalkhoran, Omid
2014
74 C p. 201-212
12 p.
artikel
24 Technology readiness assessment of partitioning and transmutation in Japan and issues toward closed fuel cycle Ikeda, Kazumi
2014
74 C p. 242-263
22 p.
artikel
25 Thermal hydraulic behavior under Station Blackout for CANDU6 Tong, L.L.
2014
74 C p. 176-183
8 p.
artikel
26 Uncertainty evaluation of the Chexal–Lellouche correlation for void fraction in rod bundles Griffiths, M.J.
2014
74 C p. 143-153
11 p.
artikel
                             26 gevonden resultaten
 
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