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                             31 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Analysis of cladding failure in a BWR fuel rod using a SLICE-DO model of the FALCON code Khvostov, G.

52 12 p. 2887-2900
artikel
2 Analysis of the first core of the Indonesian multipurpose research reactor RSG-GAS using the Serpent Monte Carlo code and the ENDF/B-VIII.0 nuclear data library Hartanto, Donny

52 12 p. 2725-2732
artikel
3 Analytic responses of slender beams supported by rotationally restrained hinges during support motions Ryu, Jeong Yeon

52 12 p. 2939-2948
artikel
4 Analyzing local perceptions toward the new nuclear research reactor in Thailand Tantitaechochart, Sarasinee

52 12 p. 2958-2968
artikel
5 An assessment of the applicability of multigroup cross sections generated with Monte Carlo method for fast reactor analysis Lin, Ching-Sheng

52 12 p. 2733-2742
artikel
6 A new perspective towards the development of robust data-driven intrusion detection for industrial control systems Ayodeji, Abiodun

52 12 p. 2687-2698
artikel
7 Application of deep neural networks for high-dimensional large BWR core neutronics Abu Saleem, Rabie

52 12 p. 2709-2716
artikel
8 Calculation of fuel temperature profile for heavy water moderated natural uranium oxide fuel using two gas mixture conductance model for noble gas Helium and Xenon Jha, Alok

52 12 p. 2760-2770
artikel
9 CFD study of the PTS experiment in ROCOM test facility Čarija, Zoran

52 12 p. 2803-2811
artikel
10 Code development on steady-state thermal-hydraulic for small modular natural circulation lead-based fast reactor Zhao, Pengcheng

52 12 p. 2789-2802
artikel
11 Comprehensive validation of silicon cross sections Czakoj, Tomáš

52 12 p. 2717-2724
artikel
12 Conceptual design of small modular reactor driven by natural circulation and study of design characteristics using CFD & RELAP5 code Kim, Mun Soo

52 12 p. 2743-2759
artikel
13 Crack growth analysis and remaining life prediction of dissimilar metal pipe weld joint with circumferential crack under cyclic loading Murthy, A. Ramachandra

52 12 p. 2949-2957
artikel
14 Effects of house load operation on PSA based on operational experiences in Korea Lim, Hak Kyu

52 12 p. 2812-2820
artikel
15 Entropy and exergy analysis and optimization of the VVER nuclear power plant with a capacity of 1000 MW using the firefly optimization algorithm Talebi, Saeed

52 12 p. 2928-2938
artikel
16 Evaluation of the radiation damage effect on mechanical properties in Tehran research reactor (TRR) clad Amirkhani, Mohamad Amin

52 12 p. 2975-2981
artikel
17 Experimental study of bubble flow behavior during flow instability under uniform and non-uniform transverse heat distribution Al-Yahia, Omar S.

52 12 p. 2771-2788
artikel
18 Improved prediction model for H2/CO combustion risk using a calculated non-adiabatic flame temperature model Kim, Yeon Soo

52 12 p. 2836-2846
artikel
19 Is nuclear energy a better alternative for mitigating CO2 emissions in BRICS countries? An empirical analysis Hassan, Syed Tauseef

52 12 p. 2969-2974
artikel
20 Microstructure evolution and effect on deuterium retention in oxide dispersion strengthened tungsten during He+ irradiation Ding, Xiao-Yu

52 12 p. 2860-2866
artikel
21 Novel homogeneous burnable poisons in pressurized water reactor ceramic fuel Dodd, Brandon

52 12 p. 2874-2879
artikel
22 On-site water level measurement method based on wavelength division multiplexing for harsh environments in nuclear power plants Lee, Hoon-Keun

52 12 p. 2847-2851
artikel
23 Parameter importance ranking for SBLOCA of CPR1000 with moment-independent sensitivity analysis Xiong, Qingwen

52 12 p. 2821-2835
artikel
24 Performance of 3D printed plastic scintillators for gamma-ray detection Kim, Dong-geon

52 12 p. 2910-2917
artikel
25 Restoration of the isotopic composition of reprocessed uranium hexafluoride using cascade with additional product Palkin, Valerii

52 12 p. 2867-2873
artikel
26 Simplified elastic-plastic analysis procedure for strain-based fatigue assessment of nuclear safety class 1 components under severe seismic loads Kim, Jong-Sung

52 12 p. 2918-2927
artikel
27 Simulation, design optimization, and experimental validation of a silver SPND for neutron flux mapping in the Tehran MTR Saghafi, Mahdi

52 12 p. 2852-2859
artikel
28 Technical Reviewers 2020
52 12 p. I-XXII
artikel
29 Thermal creep behavior of CZ cladding under biaxial stress state Xin, Jin

52 12 p. 2901-2909
artikel
30 Thermodynamic and experimental analyses of the oxidation behavior of UO2 pellets in damaged fuel rods of pressurized water reactors Jung, Tae-Sik

52 12 p. 2880-2886
artikel
31 Three-D core multiphysics for simulating passively autonomous power maneuvering in soluble-boron-free SMR with helical steam generator Abdelhameed, Ahmed Amin E.

52 12 p. 2699-2708
artikel
                             31 gevonden resultaten
 
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