Digitale Bibliotheek
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                             66 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 A cross-section correction model for history effect treatment in pin-by-pin code NECP-Bamboo2.0 Wang, Sicheng

194 C p.
artikel
2 An alternative approach for excess reactivity control of TRISO particles Razu, Fahim Mahmud

194 C p.
artikel
3 Analysis and sensitivity study of steam explosion loads Wei, Linkai

194 C p.
artikel
4 Analysis of the stress field in the reactor vessel of the China Initiative Accelerator Driven System during postulated ULOF and UTOP transients Huang, Zi-Nan

194 C p.
artikel
5 Analysis of transient measurements with thermal feedback and coupled TRACE/PARCS calculations performed on the BME Training Reactor Ványi, A.Sz.

194 C p.
artikel
6 An improved frequency-domain model for the supercritical flow instability analysis in vertical tubes Bi, Lingfeng

194 C p.
artikel
7 A novel transfer CNN with spatiotemporal input for accurate nuclear power fault diagnosis under different operating conditions Liu, Jie

194 C p.
artikel
8 A numerical benchmark for modelling phase change in molten salt reactors Pater, Mateusz

194 C p.
artikel
9 A parallel strategy applied to the simplified thermal-hydraulic part of system program Guo, Yingran

194 C p.
artikel
10 Application of Data-Driven technology in nuclear Engineering: Prediction, classification and design optimization Hong, Qiao

194 C p.
artikel
11 Application of deep learning techniques for nuclear power plant transient identification Ramezani, Iman

194 C p.
artikel
12 Benchmark analysis of the FFTF LOSWOS test #13 with OpenMC and THACS Zhou, Lei

194 C p.
artikel
13 Calculation scheme for thermal neutron scattering cross-sections of hydrogenous molecules in liquid and solid phases by molecular dynamics Abe, Y.

194 C p.
artikel
14 Comparative study of two quick-analysis models for frozen startup of high-temperature heat pipes Zhang, Lingyi

194 C p.
artikel
15 Compressible multicomponent flow simulations and data-driven modeling of high-speed liquid droplet impingement Fujisawa, Kei

194 C p.
artikel
16 Conservative evaluation of radionuclides release for VVER-440 and VVER-1000 type reactors Berezhnyi, A.

194 C p.
artikel
17 Critical heat flux and heat transfer behaviors on aged RPV outer wall surface in flow boiling under IVR conditions Liu, Pengfei

194 C p.
artikel
18 Development of deep convolutional neural network for prediction of cycle maximum pin power peaking factor in pressurized water reactor Nam, Younduk

194 C p.
artikel
19 Direct Bayesian inference for fault severity assessment in Digital-Twin-Based fault diagnosis Nguyen, Tat Nghia

194 C p.
artikel
20 Dynamical analysis of position-sensitive water-robot in radioactively contaminated areas by machine learning (ML) algorithm Ho Woo, Tae

194 C p.
artikel
21 Editorial Board
194 C p.
artikel
22 Effective medium temperature for calculating the deformed Doppler broadening function considering the Tsallis distribution Silva, Marcelo V.

194 C p.
artikel
23 Effects of rolling motion on helical coil once-through steam generator thermal-hydraulic characteristics Hou, Yandong

194 C p.
artikel
24 Evaluation of SCALE, Serpent, and MCNP for Molten Salt Reactor applications using the MSRE Benchmark Clarno, Kevin T.

194 C p.
artikel
25 Experimental research on liquid entrainment in the inclined up tee branch Zhang, Kui

194 C p.
artikel
26 Experimental study on flow split and pressure drop characteristics in a 3 × 3 dual-cooled annular rod bundle Gui, Miao

194 C p.
artikel
27 Experimental study on passive plate pitching and coherent structures in a square channel by TR-PIV Qu, Wenhai

194 C p.
artikel
28 Experimental study on the flow characteristics of 7-pin hexagonal bundle assembly with grid spacers Li, Rongjie

194 C p.
artikel
29 Experiment and new analysis model simulating in-place cooling of a degraded core in severe accidents of sodium-cooled fast reactors Imaizumi, Yuya

194 C p.
artikel
30 Expressions of electron escape probability and photo-emission from metals Liu, Yi-Fan

194 C p.
artikel
31 Failure mechanisms of equipment hatch area in prestressed concrete containment vessel Guo, Junying

194 C p.
artikel
32 Impact of the resonance elastic scattering on reactor-core physics calculation results based on the deterministic method Zhao, Miao

194 C p.
artikel
33 Improved fault diagnosis method of electric gate valve in nuclear power plant Huang, Xue-ying

194 C p.
artikel
34 Influence of interaction among multiple cracks on crack propagation in nozzle corner of reactor pressure vessel Cheng, YanTing

194 C p.
artikel
35 Irradiation experiments of titanium beryllide samples in the WWR-K reactor Shaimerdenov, A.

194 C p.
artikel
36 Method for solving atmospheric dispersion parameters of radioactive aerosols based on wind-tunnel laser measurement experiments Gu, Weiguo

194 C p.
artikel
37 Modeling noise experiments performed at AKR-2 and CROCUS zero-power reactors Hursin, M.

194 C p.
artikel
38 Multigroup covariance matrix self-shielding effects for thermal reactors fueled with slightly enriched uranium dos Santos, Adimir

194 C p.
artikel
39 Multi-objective optimization method for reactor shielding design based on SMS-EMOA Li, Xiaomeng

194 C p.
artikel
40 Multi-objective optimization of method of characteristics parameters based on genetic algorithm Song, Qufei

194 C p.
artikel
41 Multiphysics coupling analysis of heat pipe reactor based on OpenMC and COMSOL Multiphysics Wu, Aoguang

194 C p.
artikel
42 Neutronic and thermal hydraulic analysis of a PWR fuel assembly using uranium mononitride Silva, Raphael H.M.

194 C p.
artikel
43 Numerical study of the impact of blockages on the Thermal-Hydraulic performance of 19 and 61-pin Wire-Wrapped bundles with conjugate heat transfer using RANS Bovati, Octavio

194 C p.
artikel
44 Numerical study on a semi-mechanistic wall boiling model based on dry-patch mechanism for CHF prediction in vertical tube and fuel assembly Zhang, Xiang

194 C p.
artikel
45 Optimal rule based fuzzy-PI controller for core power control of nuclear reactor Acharya, Debasis

194 C p.
artikel
46 Performance analysis of heat pipe-based passive in-core decay heat removal system for the small modular reactor design with MARS-KS code Kim, Ji Yong

194 C p.
artikel
47 Performance evaluation of a high flow rate annular linear induction pump using a simple equivalent circuit model taking into account dynamic end effects Lo Pinto, Emmanuel

194 C p.
artikel
48 Photo-neutron production of medical linear accelerator Elekta, precise model: A study with the Geant4 MC toolkit Farrag, Emad A.M.

194 C p.
artikel
49 Preliminary development and verification of an OpenFOAM-based multi-physics coupling safety analysis code for Lead-based reactor Ou, Wenlan

194 C p.
artikel
50 Preliminary verification of the MCNP perturbation and fixed-source tally sensitivity tools Lamproe, Juliann R.

194 C p.
artikel
51 Probabilistic radwaste characterization: Findings of a multi-method multi-mockup exercise using interpolation-based surrogate efficiencies Laloy, Eric

194 C p.
artikel
52 Ranking of nuclear data contributions to uncertainties in core physics parameters Lindley, B.A.

194 C p.
artikel
53 Rapidly treatment of simulated An 4+ radioactive contaminated soil by microwave sintering: The influence of Al/Si ratio and mechanism Wang, Jiahong

194 C p.
artikel
54 Reactivity calculation in molten salt reactors with inverse kinetics model Diniz, Rodrigo Costa

194 C p.
artikel
55 Research on fault diagnosis method of electric gate valve under strong background noise Huang, Xue-ying

194 C p.
artikel
56 Research on the influence law of submerged depth and flow rate of diversion canal on free surface vortex in coastal nuclear power plant Bin, Lin

194 C p.
artikel
57 Retrieval and processing of radioactive muck settled in the bottom of radioactive liquid waste storage tanks Prakash, Amrita Dhara

194 C p.
artikel
58 Seismic experiments on short coaxial multi-layered cylindrical shells with fluid–structure interaction in fast reactors Zhao, Fei

194 C p.
artikel
59 Study on the effect of ocean rolling motion on the thermal–hydraulic performance of supercritical carbon dioxide in horizontal tube Shao, Huaishuang

194 C p.
artikel
60 Thermal-Hydraulic modelling and analysis of VVER-1200 reactor core El-Morshedy, Salah El-Din

194 C p.
artikel
61 Thermal neutron capture cross-section and resonance integral measurements of 186W(n,γ)187W reaction using the thermal column neutron source at the Dalat research reactor Tu Anh, Trinh T.

194 C p.
artikel
62 Three-dimensional numerical research on coupling heat transfer characteristics of PRHR HX under different water levels based on the experimental model Liu, Jingwen

194 C p.
artikel
63 Time dependent full-core multiphysics analysis of nuclear thermal propulsion reactors Krecicki, M.

194 C p.
artikel
64 Transient thermal–hydraulic analysis of the thermionic space reactor TOPAZ-II Wu, Zongyun

194 C p.
artikel
65 Uncertainty analysis of dynamic mode decomposition for xenon dynamic forecasting Liu, Jianpeng

194 C p.
artikel
66 Verification of Feynman-α formula including the effect of delayed neutrons Yamamoto, Toshihiro

194 C p.
artikel
                             66 gevonden resultaten
 
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