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                             32 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Advances in time-dependent Monte Carlo simulations for void velocity determination using neutron noise techniques Yamamoto, Toshihiro

138 C p.
artikel
2 A multi-level fuzzy switching control method based on fuzzy multi-model and its application for PWR core power control Zeng, Wenjie

138 C p.
artikel
3 An innovation idea for SBLOCA mitigation strategy: Self-coagulation system in comparison with human hemostatic mechanism Cheng, Hui

138 C p.
artikel
4 Application of Hazard and Operability Technique to Level 1 Probabilistic Safety Assessment of Thai Research Reactor-1/Modification 1: Internal Events and Human Errors Vechgama, Wasin

138 C p.
artikel
5 A survey of multi-objective optimization methods and their applications for nuclear scientists and engineers Stewart, Ryan H.

138 C p.
artikel
6 Challenges and progress of uncertainty analysis for the pebble-bed high-temperature gas-cooled reactor Guo, Jiong

138 C p.
artikel
7 CHF enhancement for a finned surface in flow boiling with explanations based on vapor observations Wang, Kai

138 C p.
artikel
8 3D-2D coupling multi-dimension simulation for the heat pipe micro-reactor by MOOSE&SAM Zhou, Yukun

138 C p.
artikel
9 Design, fabrication and characterization of neutron irradiation facility using accelerator-based photoneutron source Eshwarappa, K.M.

138 C p.
artikel
10 Development and verification of neutron and photon multi-group cross sections processing code TXMAT2.0 Zhang, Bin

138 C p.
artikel
11 Development of a new method to determine the axial void velocity profile in BWRs from measurements of the in-core neutron noise Pázsit, Imre

138 C p.
artikel
12 Editorial Board
138 C p.
artikel
13 Evaluation of various active nucleation site density models of subcooled flow boiling in a vertical tube using OpenFOAM Yang, Chunbang

138 C p.
artikel
14 Heat transport and chimney design in a typical MTR reactor during natural convection cooling regime Abdelmaksoud, Abdelfatah

138 C p.
artikel
15 Insights from the analysis of flooding-related international operating experience at NPPs Šimić, Zdenko

138 C p.
artikel
16 Interaction between caesium iodide particles and gaseous boric acid in a flowing system through a thermal gradient tube (1030 K–450 K) and analysis with ASTEC/SOPHAEROS Gouëllo, Mélany

138 C p.
artikel
17 Investigation of air-water two-phase flow characteristics in a 25.4 mm diameter circular pipe Wang, Dewei

138 C p.
artikel
18 Multi-criteria comparison of nuclear reactors using the MULTIMOORA method: A case of study for Chile Fernández, Claudio

138 C p.
artikel
19 Nanofluid application for heat transfer, safety, and natural circulation enhancement in the NuScale nuclear reactor as a small modular reactor using computational fluid dynamic (CFD) modeling via neutronic and thermal-hydraulics coupling Rahnama, Z.

138 C p.
artikel
20 Numerical investigation of gas-liquid two-phase flow in horizontal pipe with orifice plate Zhang, Yu

138 C p.
artikel
21 Optical and gamma-ray shielding effectiveness of a newly fabricated P2O5–CaO–Na2O–K2O–PbO glass system Alotaibi, B.M.

138 C p.
artikel
22 Power optimization and ripple minimization in switched reluctance motor drives of small modular reactor and a comparison with a permanent magnet motor Mohammadi, Farzaneh

138 C p.
artikel
23 Preliminary feasibility analysis of Heat Pipe Cooled Bimodal Space Nuclear Reactor Tian, Xiaoyan

138 C p.
artikel
24 Review of nuclear microreactors: Status, potentialities and challenges Testoni, Raffaella

138 C p.
artikel
25 Single-phase density wave oscillation -A new mechanism of flow instability in inverted U-type steam generator Ma, Zaiyong

138 C p.
artikel
26 Sorption of U(VI) ions from aqueous solution by eggplant leaves: Isotherm, kinetics and thermodynamics studies Mahmoud, Mohamed Ahmed

138 C p.
artikel
27 Status, opportunities, and challenges of nuclear power development in Sub-Saharan Africa: The case of Ghana Adams, Samuel

138 C p.
artikel
28 The operational assessment of steam generator tubes based on a stochastic crack growth model Francisco, A.S.

138 C p.
artikel
29 Thermal-hydraulic test facility for nuclear reactor containment: Engineering design methodology and benchmarking Punetha, Maneesh

138 C p.
artikel
30 Three-dimensional methodology to predict reversed flow in primary side of U-tube steam generator Cong, Tenglong

138 C p.
artikel
31 Two-stage modelling of hexagonal fuel assemblies vibration considering mechanical nonlinearities Zeman, V.

138 C p.
artikel
32 Young Chinese people's radiological beliefs significantly associated with their opinions on nuclear power Wu, Hsingtzu

138 C p.
artikel
                             32 gevonden resultaten
 
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