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                             39 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 An assessment of PWR fuel assembly spacer grid strength by FEM models Hakam Adli, Naqeeb

198 C p.
artikel
2 An innovative neutronic deterministic scheme for moderator high-void effect calculation in PWR partially loaded with MOX assemblies De Mattei, Sébastien

198 C p.
artikel
3 Application of CFD and nodal expansion method for simulation and analysis of boron dilution accident Kolali, Ali

198 C p.
artikel
4 Bayesian calibration and fitting of nuclear thermal–hydraulic models by Markov chain Monte Carlo methods using the Gibbs sampler Muñoz-Cobo, José L.

198 C p.
artikel
5 Calculate of an additional resistance with reverse flow in steam generator under steady-state conditions Rao, Yuxian

198 C p.
artikel
6 CFD analysis of PHWR exposed core under postulated severe accident condition Rajaganesh, S.

198 C p.
artikel
7 CMT and PBL study in the high-pressure phase on the advance core-cooling mechanism experiment with RELAP 5 Yeh, Szu-En

198 C p.
artikel
8 Comprehensive analysis of ASTRA benchmark with MCU-HTR and Serpent codes Kruglikov, A.E.

198 C p.
artikel
9 Coupled Computational Fluid Dynamics and Computational Thermodynamics Simulations for Chemically Reacting Flows with Phase Transformations: A Fluoride Volatility Process Example Scuro, N.L.

198 C p.
artikel
10 Criticality safety of fuel assemblies with missing fuel rods Dechenaux, Benjamin

198 C p.
artikel
11 Deterministic neutron transport and burnup code coupling assessment Vivancos, Arturo

198 C p.
artikel
12 Development and benchmarking of space-time kinetics solver in REDAC Kale, Vivek A.

198 C p.
artikel
13 Development of Nusselt number and friction factor models for rough rod bundles based on wall functions Wang, Xiaowen

198 C p.
artikel
14 Dimensionality reduction combined with particle swarm optimization algorithm for solving high-dimensional nuclear data target accuracy evaluation problem Qin, Kaiwen

198 C p.
artikel
15 DNBR limit analysis for the inner channel of annular fuel Guo, Junliang

198 C p.
artikel
16 Editorial Board
198 C p.
artikel
17 Experimental modeling of slip velocity in an L-shape pulsed packed extraction column using response surface methodology Khooshechin, Sajad

198 C p.
artikel
18 Experimental study on flow-induced vibration of single rod in axial flow Wang, Ningyuan

198 C p.
artikel
19 Experimental study on scaled-down pads for nuclear main pump thrust bearing Li, Qiang

198 C p.
artikel
20 Experimental study on the influence of velocity on hydraulic characteristics in reactor lower plenum Peng, Fan

198 C p.
artikel
21 Fine-mesh homogenization and anisotropic SP3 calculation for PWR cores with plate-type fuel and strong absorbers Li, Yunzhao

198 C p.
artikel
22 HK-SPSA based performance optimization method for steam generator liquid level control Yang, Zean

198 C p.
artikel
23 Iodine source term assessment as result of iodine spiking and mass transfer phenomena during a SGTR transient using MELCOR 2.2 and CATHARE 2 codes Foucaud, P.

198 C p.
artikel
24 Irradiation dose and temperature effects on BCC material with dislocation based crystal plasticity Singh, Kulbir

198 C p.
artikel
25 Measurement of prompt neutron capture gamma coming from iron and chlorine Czakoj, Tomáš

198 C p.
artikel
26 Mössbauer spectroscopy and gamma-ray shielding performance for iron phosphate glasses containing various heavy metals oxides Abdelwahab, B.

198 C p.
artikel
27 Nodal expansion method based reduced-order model for control rod movement Wang, Yahui

198 C p.
artikel
28 Numerical investigation of the maximum temperature zone for liquid–vapour flow during reflooding Cheng, Yixuan

198 C p.
artikel
29 Numerical simulation analysis of debris filtration in the bottom nozzle Deng, Shuang

198 C p.
artikel
30 Numerical simulation of safety injection and natural circulation in two containers by smoothed particle hydrodynamics on the effects of filling levels and thermal diffusivities Cao, Can

198 C p.
artikel
31 Pressure fluctuations preceding critical heat flux during subcooled flow boiling in a one-side heated mini-channel under rolling motion Aziz, Faraz

198 C p.
artikel
32 Radiation effect assessment on spent fuel transport CASK by aircraft sabotage attack Ho Park, Ki

198 C p.
artikel
33 Reproducible benchmark for the SNAP 8 experimental reactor at dry conditions Garcia, Samuel

198 C p.
artikel
34 Research progress of plasma melting technology in radioactive waste treatment of nuclear power plants Ma, Yuheng

198 C p.
artikel
35 Role of internal heat generation, magnetism and Joule heating on entropy generation and mixed convective flow in a square domain Deb, Niloy

198 C p.
artikel
36 Safety analysis of pressurized water reactors with annular fuel during different transients Yang, Bowen

198 C p.
artikel
37 Study on multi-scale coupled simulation of natural circulation system with 3 × 3 petal-shaped fuel bundle channel under rolling condition Cao, Jinyi

198 C p.
artikel
38 Study on operation characteristics of a compact megawatt nuclear power system Zhang, Minghui

198 C p.
artikel
39 Uniformity of neutron absorber distribution in Gd-containing neutron absorber materials Kwon, Junhyun

198 C p.
artikel
                             39 gevonden resultaten
 
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