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                             60 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Adsorption removal of uranium from aqueous solution by hydroxyapatite: Recent advances and prospects Wu, Wenjun

206 C p.
artikel
2 Analysis of a PSB-VVER small break LOCA experiment with APROS and TRACE system codes Varju, Tamás

206 C p.
artikel
3 Analysis of the critical parameters for tritiated water entrained moist gas emission from nuclear power station Xu, Xi

206 C p.
artikel
4 An Enkf-based data assimilation method and its application in a narrow rectangular channel Chen, Wuguang

206 C p.
artikel
5 A new equivalent radiation source method for the reconstruction of nuclear radiation field Zhou, Yan

206 C p.
artikel
6 An experimental study on the impact of particle surface wettability on melt infiltration in particulate beds Chen, Liang

206 C p.
artikel
7 Applicability of a proper orthogonal decomposition-based online power-distribution reconstruction code to detector reduction Li, Zhuo

206 C p.
artikel
8 A PWR core power control using optimized PID controller with SQP based on control rod positioning and variable coolant flow rate Salman, Ahmed E.

206 C p.
artikel
9 A study on bubble entrainment rate in a decaying swirling flow field based on the wire-mesh sensor Zhang, Jiarong

206 C p.
artikel
10 Asymptotic expressions for the Tsallis Doppler Broadening Function Cunha, Johann Alexandre Rodrigues

206 C p.
artikel
11 CFD investigation on start-up transient of HPR1000 secondary side passive residual heat removal heat exchanger Lang, Xutong

206 C p.
artikel
12 Clustering and uncertainty analysis to improve the machine learning-based predictions of SAFARI-1 control follower assembly axial neutron flux profiles Moloko, Lesego E.

206 C p.
artikel
13 Concentration level of radionuclides in road dust in the urban atmosphere of two cities of Pakistan Baloch, Muzahir Ali

206 C p.
artikel
14 Corrigendum to “REGAL international program: Analysis of experimental data for depletion code validation” [Annals Nucl. Energy 172 (2022) 109057] Eysermans, J.

206 C p.
artikel
15 Design and cooling of permanent magnet generator in MW-class space closed Brayton cycle system Yang, Chuping

206 C p.
artikel
16 Design of an integrated simulation platform and its application to control system for supercritical CO2 Brayton cycle cooled reactor system Jillani, Ghulam

206 C p.
artikel
17 Development of a solidification blockage discriminant model in filling pipelines Zeng, Chen

206 C p.
artikel
18 Development of the thermal hydraulic analysis code, TASS/SMR-S, under multi-dimensional motion for a reactor under inclination and rolling conditions Kim, Jeong Eun

206 C p.
artikel
19 Editorial Board
206 C p.
artikel
20 Effectiveness analysis of containment hydrogen combination system in HPR1000 nuclear power plant Geng, Fengxiang

206 C p.
artikel
21 Effect of inertial pressure on criticality excursion and radiolytic gas bubbles for fuel solution system Sheng, Huimin

206 C p.
artikel
22 Effect of non-uniform inflow on vortex structure of a small modular reactor coolant pump Long, Yun

206 C p.
artikel
23 Effect of passive auxiliary feedwater system on mitigation of DEC accidents: Part I. MSGTR, SBLOCA-LOSI, and SBO Park, Youngjae

206 C p.
artikel
24 Effects of internal heat production and Joule heating on MHD conjugate mixed convection and entropy production inside a thermally non-homogeneous cooling system Hasan, Nahid

206 C p.
artikel
25 Efficient simulation time reduction in uncertainty quantification via the polynomial chaos expansion method Jang, Jaerim

206 C p.
artikel
26 Evaluating security risk among source operators in nuclear and radiological facilities Shafiqul Islam, Md.

206 C p.
artikel
27 Evaluation of reflector design of ALLEGRO refractory core Pónya, P.

206 C p.
artikel
28 Experimental investigation of quench front propagation during reflooding in 5 × 5 rod bundle channel with axial uniform power distribution Liu, Weihua

206 C p.
artikel
29 Experimental study on leakage of high-energy fluids through narrow elliptical slits Zhang, Tao

206 C p.
artikel
30 Influence of moderator temperature on fuel channel behaviour under PT-CT contact during LOCA for Indian PHWR Bhadauria, Madhuri

206 C p.
artikel
31 Investigation of molten fuel coolant interaction with simulated corium in sodium Hemanth Rao, E.

206 C p.
artikel
32 Low precision preconditioning for solving neutron diffusion eigenvalue problem by finite element method Cherezov, Alexey

206 C p.
artikel
33 Measurement of spectrum averaged cross sections in LR-0 benchmark reference neutron field Košťál, Michal

206 C p.
artikel
34 Minimum dose walking path planning in a nuclear radiation environment based on a modified A* algorithm Zhang, Biao

206 C p.
artikel
35 Multi-physics coupling behaviors on 3 × 3 helical cruciform fuel rods of U-50Zr alloy under normal and accident conditions Cai, Mengke

206 C p.
artikel
36 New analysis model of solid body formation in particle method for jet impingement and solidification in severe accidents of SFRs Imaizumi, Yuya

206 C p.
artikel
37 New burst criteria for loss of coolant accidents radiological consequences assessment Taurines, Tatiana

206 C p.
artikel
38 Numerical investigation on subcooled boiling and CHF characteristics in 3 × 3 petal-shaped fuel rod bundle channel under cosine heating condition Cai, Weihua

206 C p.
artikel
39 Numerical prediction of the heat transfer properties of Flinabe molten salt as a coolant in a nuclear system Shishido, Hiroki

206 C p.
artikel
40 Numerical research on the influence of ocean conditions on the transient response of passive decay heat removal system of the floating Fluoride-Salt-Cooled High-Temperature Reactors Liu, Limin

206 C p.
artikel
41 Numerical simulation of axial and radial decay heat distribution in spent RBMK-1500 fuel assembly Slavickas, Andrius

206 C p.
artikel
42 Numerical study on thermal–hydraulic behaviors of a natural circulation system with petal-shaped fuel rod bundle Sun, Jian-Chuang

206 C p.
artikel
43 Performance evaluation and validation of OpenMC code for criticality analysis of an MTR-type research reactor Lababsa, Djahid

206 C p.
artikel
44 Reduced-order methods for neutron transport kinetics problem based on proper orthogonal decomposition and dynamic mode decomposition Chi, Honghang

206 C p.
artikel
45 Research on gas–liquid two-phase transient process of reactor coolant pump under stuck shaft accident Wang, Xiuli

206 C p.
artikel
46 Research on operating characteristics of AP1000 automatic depressurization system under typical accident condition Shang, Zhengrun

206 C p.
artikel
47 Research on reliability assessment approach of marine passive safety system based on improved Kriging model and SORM Bi, Yuepeng

206 C p.
artikel
48 Review of research and capabilities of 500 kW research reactor at the Ohio State University Kauffman, Andrew

206 C p.
artikel
49 Simulation and experimental study of the effect of thrust bearing with worn pads on lubrication performance Xie, Quntao

206 C p.
artikel
50 STAR-CCM+ simulation of debris bed formation in the unheated DEFCON-S experiment Eom, Jeong-Hyeon

206 C p.
artikel
51 Study on the effect of magnetic field on uranium dendrite growth by phase field method Zhou, Wentao

206 C p.
artikel
52 The conceptual design of emergency core cooling scheme for Tsinghua high flux reactor Wang, Zhuang

206 C p.
artikel
53 The effect of oil shale ash and basalt-boron fiber on waste package gamma-radiation shielding properties Tohver, Hando

206 C p.
artikel
54 The Effects of Edge Dislocations on The Corrosion Behavior of Pure Iron in Liquid Lead-Bismuth Eutectic: A Molecular Dynamics Study Chen, Liming

206 C p.
artikel
55 The improved odCMFD method accelerated for quasi-3D method based on Fourier analysis Zhou, Xinyu

206 C p.
artikel
56 The multi-level acceleration methodology for the high-fidelity transient simulation of the nuclear reactor Li, PeiJun

206 C p.
artikel
57 Thermal-hydraulic characteristics of helical cruciform single rod based on CFD investigation Chen, Yiwen

206 C p.
artikel
58 Triangular polynomial expansion nodal method in AGREE Kochunas, Brendan

206 C p.
artikel
59 Verification and validation of seven turbulence models for a natural circulation loop under transient conditions Angelo, G.

206 C p.
artikel
60 Water level control of U-tube steam generator based on model-based active disturbance rejection control method Ma, Qian

206 C p.
artikel
                             60 gevonden resultaten
 
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