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 |