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                             35 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A comparative study of station blackout scenario dynamics initiated by internal and seismic event in boiling water reactor Park, Sanggil
2017
108 C p. 329-342
artikel
2 A full life cycle nuclear knowledge management framework based on digital system Wang, Minglu
2017
108 C p. 386-393
artikel
3 A hybrid pile oscillator experiment in the Minerve reactor Geslot, Benoit
2017
108 C p. 268-276
artikel
4 An advanced new fully implicit numerical method for two-phase flow subchannel analysis based on the Drift Flux Model Hajizadeh, A.
2017
108 C p. 351-365
artikel
5 A study of insider threat in nuclear security analysis using game theoretic modeling Kim, Kyo-Nam
2017
108 C p. 301-309
artikel
6 A study of reactivity biases and their dependence on spatial discretization in depleted TRIGA fuel Cheng, Ye
2017
108 C p. 126-131
artikel
7 Comparison of ASME pressure–temperature limits on the fracture probability for a pressurized water reactor pressure vessel Chou, Hsoung-Wei
2017
108 C p. 366-375
artikel
8 Core optimisation issues of MOX fueled ALLEGRO reactor Pónya, P.
2017
108 C p. 188-197
artikel
9 Editorial board 2017
108 C p. IFC
artikel
10 Effect of in-core instrumentation mounting location on external reactor vessel cooling Suh, Jungsoo
2017
108 C p. 89-98
artikel
11 Estimation of axial xenon oscillations with online parameter adaptation in the P.W.R nuclear reactors using Lyapunov approach based on the multipoint kinetics reactor model Zaidabadi nejad, M.
2017
108 C p. 277-300
artikel
12 Failure mode taxonomy for assessing the reliability of Field Programmable Gate Array based Instrumentation and Control systems McNelles, Phillip
2017
108 C p. 198-228
artikel
13 Flow and heat transfer analyses of a plate-fin heat exchanger in an HTGR Chen, Tao
2017
108 C p. 316-328
artikel
14 Generalized Iterated Fission Probability for Monte Carlo eigenvalue calculations Terranova, Nicholas
2017
108 C p. 57-66
artikel
15 Improved discrete nodal transport method for treating void regions Xu, Zhitao
2017
108 C p. 172-180
artikel
16 Inverse kinetics for subcritical systems with external neutron source de Carvalho Gonçalves, Wemerson
2017
108 C p. 343-350
artikel
17 Investigation on two-phase distribution in a vibrating annulus Xiao, Xiu
2017
108 C p. 67-78
artikel
18 Modeling of FREYA fast critical experiments with the Serpent Monte Carlo code Fridman, E.
2017
108 C p. 239-252
artikel
19 Multi-hazard performance of reinforced concrete dry casks subjected to chloride attack and tip-over impact Hanifehzadeh, Mohammad
2017
108 C p. 10-23
artikel
20 Non-linear boiling water reactor stability with Shannon Entropy Olvera-Guerrero, Omar Alejandro
2017
108 C p. 1-9
artikel
21 Reloading pattern optimization of VVER-1000 reactors in transient cycles using genetic algorithm Rahmani, Yashar
2017
108 C p. 24-41
artikel
22 Risk assessment of safety data link and network communication in digital safety feature control system of nuclear power plant Lee, Sang Hun
2017
108 C p. 394-405
artikel
23 Scaling analysis of the spreading and deposition behaviors of molten-core-simulated metals Matsumoto, Tatsuki
2017
108 C p. 79-88
artikel
24 Solution of the neutron transport equation by the Method of Characteristics using a linear representation of the source within a mesh Mazumdar, Tanay
2017
108 C p. 132-150
artikel
25 Stand-alone core sensitivity and uncertainty analysis of ALFRED from Monte Carlo simulations Pérez-Valseca, A.-D.
2017
108 C p. 113-125
artikel
26 Status of dynamic water film model development in 3-D CFD code GASFLOW-MPI for analysis of passive containment cooling system Xiao, Jianjun
2017
108 C p. 99-112
artikel
27 Structural analysis of the CAREM-25 nuclear power plant subjected to the design basis accident and seismic loads Ambrosini, Daniel
2017
108 C p. 42-56
artikel
28 The ADO-nodal method for solving two-dimensional discrete ordinates transport problems Barichello, L.B.
2017
108 C p. 376-385
artikel
29 The impacts of random effect and scattering effects on the neutronics analysis of the PB-FHR Li, Zhifeng
2017
108 C p. 163-171
artikel
30 Theoretical analysis and evaluation for neutron-induced reaction on 239Pu Guo, Hairui
2017
108 C p. 151-162
artikel
31 Thermal performance of a concrete cask: Methodology to model helium leakage from the steel canister Penalva, J.
2017
108 C p. 229-238
artikel
32 The virtual simulation system for training and demonstrating the design of the head-end of spent nuclear fuel reprocessing ZHongkun, Liu
2017
108 C p. 310-315
artikel
33 Transient analysis of AP1000 NPP under the similar Fukushima accident conditions Yang, Jiang
2017
108 C p. 181-187
artikel
34 Unsteady-state thermal stress and thermal deformation analysis for a pressurizer surge line subjected to thermal stratification based on a coupled CFD-FEM method Zhang, Y.
2017
108 C p. 253-267
artikel
35 Weibull parameter calculation and estimation of wind speeds for the return period: A case study in the Kori and Wolsong NPP areas Lee, Jong Kuk
2017
108 C p. 406-412
artikel
                             35 gevonden resultaten
 
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