Digitale Bibliotheek
Sluiten Bladeren door artikelen uit een tijdschrift
     Tijdschrift beschrijving
       Alle jaargangen van het bijbehorende tijdschrift
         Alle afleveringen van het bijbehorende jaargang
                                       Alle artikelen van de bijbehorende aflevering
 
                             41 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A comparative study of deep learning-based fault diagnosis methods for rotating machines in nuclear power plants Qian, Gensheng

178 C p.
artikel
2 A Monte Carlo-based adaptive weighted reduced order model for gamma density measurement Lin, Lvlin

178 C p.
artikel
3 Analysis of mixed convection of a power-law non-Newtonian nanofluid through a vented enclosure with rotating cylinder under magnetic field Abderrahmane, Aissa

178 C p.
artikel
4 An overall safety concept for nuclear power plants Hyvärinen, Juhani

178 C p.
artikel
5 Assessment of different internal flow blockage scenarios for LFR fuel assemblies with different configurations Luo, Xiao

178 C p.
artikel
6 Assessment of nuclear data libraries for fast reactor systems with MCNP and NDaST Zwermann, Winfried

178 C p.
artikel
7 A study on the clearance waste recycling scenario in the decommissioning of Korea’s nuclear power plants Lim, Ye-Jeon

178 C p.
artikel
8 Calculation of the VENUS-3 benchmark experiment by response-matrix and Monte Carlo methods Dorval, Eric

178 C p.
artikel
9 Calibration of an airborne γ-ray spectrometer based on an unmanned aerial vehicle using a point source Qin, Guoxiu

178 C p.
artikel
10 Characterisation of observed heat transfer deterioration modes at supercritical pressure with the aid of a CFD model Pucciarelli, A.

178 C p.
artikel
11 Code Verification and Solution Verification framework in pin-resolved neutron transport code MPACT Wang, Jipu

178 C p.
artikel
12 Computational fluid dynamic investigations of flow bypass through an aged CANDU pressure tube Lu, Z.

178 C p.
artikel
13 Core optimization of UO2 fuelled ALLEGRO reactor Pónya, P.

178 C p.
artikel
14 Decomposition of hydrogen solution in the neighborhood of the coolant saturation temperature as a possible cause of increased oxidation of VVER fuel element Ivanov, A.S.

178 C p.
artikel
15 Deep learning techniques for in-core perturbation identification and localization of time-series nuclear plant measurements Papaoikonomou, Antonios

178 C p.
artikel
16 Development of a fast thermal-hydraulic model to simulate heat and fluid flow in MNSR Abbassi, Yasser

178 C p.
artikel
17 Editorial Board
178 C p.
artikel
18 Emergency response implications of tritium in CANDU severe accidents Lebel, Luke

178 C p.
artikel
19 Emulating loss of coolant simulations in a pressurized heavy water reactor Anghel, C.V.

178 C p.
artikel
20 Evaluation of the dryout power density of a volumetrically heat-generating three-dimensional porous bed Na, Hanbee

178 C p.
artikel
21 Fragility analysis and probabilistic safety performance evaluation of nuclear containment structure under local prestressed tendons fracture conditions Jin, Song

178 C p.
artikel
22 Implementation of multi-domains in SIMMER-V thermohydraulic code Kędzierska, Barbara

178 C p.
artikel
23 Improvement of JASMINE code for ex-vessel molten core coolability in BWR Matsumoto, Toshinori

178 C p.
artikel
24 Investigation on a new scheme for the transient simulation of the research pulsed reactor Wang, Yongping

178 C p.
artikel
25 Long-term operation monitoring strategy for nuclear power plants based on continuous learning Yu, Yue

178 C p.
artikel
26 Monte Carlo calculation and similarity evaluation for verification of influential uncertainty parameters to LBLOCA derived by statistical methods Kang, Dong Gu

178 C p.
artikel
27 New approach to find the equilibrium cycle in PWR reactors using genetic algorithms Rodrigues, Pedro H.S.

178 C p.
artikel
28 Noise optimization of multi-stage orifice plates based on RBF neural network response surface and adaptive NSGA-II Gan, Runlin

178 C p.
artikel
29 Numerical investigation on heat transfer and pressure drop characteristics of moisture separator reheater with porous media method Yang, T.A.

178 C p.
artikel
30 Off-line vs. semi-implicit TH-TH coupling schemes: A BEPU comparison Casamor, M.

178 C p.
artikel
31 PCM-based uncertainty reduction in support of model validation for depletion calculations Huang, Dongli

178 C p.
artikel
32 Qualification activities of the spliced joint for CFETR Xu, Yue

178 C p.
artikel
33 Research on pressure pulsation characteristics of a reactor coolant pump in hump region Huang, Song

178 C p.
artikel
34 Safety-related parameters calculation for OPAL reactor using MCNP v6.1.0 and ENDF/B-VII.1 Ferraro, Diego

178 C p.
artikel
35 Scientific motivations for a reassessment of the neutron capture cross sections of erbium isotopes in the high-sensitivity thermal energy range for LWR systems Guglielmelli, A.

178 C p.
artikel
36 Sensitivity analysis in core diagnostics Herb, J.

178 C p.
artikel
37 Study on criteria and prediction method of liquid fall type gas entrainment in pool-type sodium-cooled fast reactors Yao, Hao

178 C p.
artikel
38 Study on the characteristics of the nuclear reactor coolant pump during the process-divided start-up period Zhang, Wenqi

178 C p.
artikel
39 Thermal-hydraulic study in a wire-wrapped 19-rod bundle based on an isotropic four-equation model Su, Xing-Kang

178 C p.
artikel
40 Verification and validation of the high-resolution code nTF with VVER-1000 hot zero power monte carlo calculations and experimental data Papadionysiou, Marianna

178 C p.
artikel
41 VITAS: A multi-purpose simulation code for the solution of neutron transport problems based on variational nodal methods Zhang, Tengfei

178 C p.
artikel
                             41 gevonden resultaten
 
 Koninklijke Bibliotheek - Nationale Bibliotheek van Nederland