| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A comparative study on the effect of reactor cavity shape and location of reactor vessel on the shape of particle bed formed in pre-flooded reactor cavity using the CFD-DEM method
|
Na, Hanbee
|
|
|
180 |
C |
p.
|
artikel
|
| 2 |
Acoustic characterization study for multi-hole orifices in nuclear piping system
|
Gan, Runlin
|
|
|
180 |
C |
p.
|
artikel
|
| 3 |
Activity inventory of activated materials in distant components of the CENM TRIGA MARK II reactor for decommissioning planning
|
El Maliki El Hlaibi, S.
|
|
|
180 |
C |
p.
|
artikel
|
| 4 |
Adsorptive removal of Sr(II) from aqueous solution by xanthate modified chitosan
|
Xu, Bowen
|
|
|
180 |
C |
p.
|
artikel
|
| 5 |
An efficient AI algorithm for fault diagnosis in nuclear power plants based on machine deep learning techniques
|
Elbordany, Ayman A.
|
|
|
180 |
C |
p.
|
artikel
|
| 6 |
An efficient method for solving flow field in high temperature gas-cooled reactor
|
Zhang, Haojie
|
|
|
180 |
C |
p.
|
artikel
|
| 7 |
A new fuel shuffling model for treating the random burnup histories of pebble-bed reactor
|
Wu, Hongwei
|
|
|
180 |
C |
p.
|
artikel
|
| 8 |
A new iterative method based on the Q-iteration method for robust and rapid determination of concentration distribution in multicomponent separation cascades
|
Wu, Ruinan
|
|
|
180 |
C |
p.
|
artikel
|
| 9 |
An improved extended CREAM model using a 2-tuple linguistic and DANP in nuclear power plants
|
Yan, Shengyuan
|
|
|
180 |
C |
p.
|
artikel
|
| 10 |
A novel Ansys CFX – RELAP5 coupling tool for the transient thermal-hydraulic analysis of liquid metal systems
|
Puviani, Pietro Cioli
|
|
|
180 |
C |
p.
|
artikel
|
| 11 |
A novel fully explicit GPU-accelerated discrete element method coupled with moving particle hydrodynamics (DEM-MPH) for simulating the underwater particle sedimentation behavior
|
Yokoyama, Ryo
|
|
|
180 |
C |
p.
|
artikel
|
| 12 |
Anti-carburization strategies for superalloys Inconel 617 and Incoloy 800H during service in VHTR coolant: Pre-oxidation and continuous oxidation
|
Du, Bin
|
|
|
180 |
C |
p.
|
artikel
|
| 13 |
Application of similarity analysis method in neutronics design of multi-purpose experimental reactor
|
Jin, Chengjian
|
|
|
180 |
C |
p.
|
artikel
|
| 14 |
A simple model of prompt neutron leakage self-multiplication for use in nuclear materials assay
|
Croft, Stephen
|
|
|
180 |
C |
p.
|
artikel
|
| 15 |
Consequence evaluation methodology for attacks on spent nuclear fuel dry casks
|
Lebel, Luke
|
|
|
180 |
C |
p.
|
artikel
|
| 16 |
Control of the VVER-1000 core power using optimized T-S fuzzy controller based on nonlinear point kinetic model
|
Salman, Ahmed E.
|
|
|
180 |
C |
p.
|
artikel
|
| 17 |
Coupling effects of bend corners with alternating direction on the heat transfer and hydraulic characteristics of zigzag-type printed circuit heat exchanger for the next generation nuclear systems
|
Chen, Shuang-qing
|
|
|
180 |
C |
p.
|
artikel
|
| 18 |
Design and optimization of a 500 kW multi-cylinder double-acting free piston stirling engine for deep-sea nuclear power system
|
Guo, Siyi
|
|
|
180 |
C |
p.
|
artikel
|
| 19 |
Development and assessment of an additional inertia force model for one-dimensional nuclear system analysis code under ocean conditions
|
Chen, Jiayue
|
|
|
180 |
C |
p.
|
artikel
|
| 20 |
Development and evaluation of a two-dimensional neutron diffusion model of a small modular heat-only reactor TEPLATOR using COMSOL
|
Ray, Dipanjan
|
|
|
180 |
C |
p.
|
artikel
|
| 21 |
Development and validation of a subchannel radiative heat transfer model for fuel bundles
|
Huang, Guolong
|
|
|
180 |
C |
p.
|
artikel
|
| 22 |
Development of a new process for the radioactive ion exchange resins conditioning - HYPEX ®
|
Crivelli, Francesca
|
|
|
180 |
C |
p.
|
artikel
|
| 23 |
Development of source term estimation model using Kalman filter technique and its evaluation against reversal method
|
Kundu, Dipan
|
|
|
180 |
C |
p.
|
artikel
|
| 24 |
Dynamic analysis code development for space nuclear power systems
|
Jiang, Baihui
|
|
|
180 |
C |
p.
|
artikel
|
| 25 |
Editorial Board
|
|
|
|
180 |
C |
p.
|
artikel
|
| 26 |
Effect of tip injection on performance of high-load helium compressor cascade in high temperature gas-cooled reactor
|
Tian, Zhitao
|
|
|
180 |
C |
p.
|
artikel
|
| 27 |
Equivalent radiation attenuation method for nuclear radiation field reconstruction
|
Zhou, Yan
|
|
|
180 |
C |
p.
|
artikel
|
| 28 |
Experimental and numerical study of single bubble migration behavior in stagnant molten LBE
|
Chen, Songhui
|
|
|
180 |
C |
p.
|
artikel
|
| 29 |
Experimental investigation of emulsion phase holdup in uranium extraction with emulsion liquid membrane technique by a pulsed packed extraction column
|
Khoshgu-Fatmeh-Sary, Fatemeh
|
|
|
180 |
C |
p.
|
artikel
|
| 30 |
Experimental research on the two-phase turbulent mixing between rod bundle subchannels with spacer grid
|
Ma, Zaiyong
|
|
|
180 |
C |
p.
|
artikel
|
| 31 |
Experimental study on condensation heat transfer of water-ethanol vapour mixtures inside inclined tubes
|
Ma, Ziqiang
|
|
|
180 |
C |
p.
|
artikel
|
| 32 |
Experimental study on startup performance of sodium heat pipe with high ratio of length-to-diameter under different coolant flow rates
|
Xu, Jun
|
|
|
180 |
C |
p.
|
artikel
|
| 33 |
Experimental study on the influence of gas injection on flashing in open natural circulation systems under stable boundary conditions
|
zhang, Shengnan
|
|
|
180 |
C |
p.
|
artikel
|
| 34 |
Feasibility of using thermoelectric generators to power monitoring platforms of SNF canister internal conditions
|
Hager, Brandon
|
|
|
180 |
C |
p.
|
artikel
|
| 35 |
Free outflow from the end of a horizontal circular pipe related to flow from the PWR cold leg to the downcomer
|
Satou, Akira
|
|
|
180 |
C |
p.
|
artikel
|
| 36 |
Generalized Hébert method for double-heterogeneity problem
|
Liang, Zhaoyu
|
|
|
180 |
C |
p.
|
artikel
|
| 37 |
GTES: A GNDS format nuclear data processing code interfacing AXSP
|
Yi, Wenming
|
|
|
180 |
C |
p.
|
artikel
|
| 38 |
HINT-Sec: Hardware-in-the-loop nuclear power plant testbed for cyber security
|
Nam, Kihaeng
|
|
|
180 |
C |
p.
|
artikel
|
| 39 |
Impact response analysis of fuel assembly based on nonlinear simplified dynamics modeling
|
Yang, Tao
|
|
|
180 |
C |
p.
|
artikel
|
| 40 |
Improved dynamic fuzzy neural network-based power control for the load following of lead-cooled fast reactor
|
Shen, Yanyi
|
|
|
180 |
C |
p.
|
artikel
|
| 41 |
Independent Nuclide Simulation Method (INSM) – A depletion algorithm for simulating the intermediate process of nuclide transmutation
|
Li, Dongyuan
|
|
|
180 |
C |
p.
|
artikel
|
| 42 |
Influence of CHF enhancement by different surfactants in TiO₂ and CNTs hybrid nanofluid on a downward heating plane
|
Wang, Weiguo
|
|
|
180 |
C |
p.
|
artikel
|
| 43 |
Intelligent control of marine second loop steam discharge system based on variable universe fuzzy control
|
Zhou, Yujin
|
|
|
180 |
C |
p.
|
artikel
|
| 44 |
Investigation on aerosol removal by spray droplets under severe accident conditions
|
Hu, Peizheng
|
|
|
180 |
C |
p.
|
artikel
|
| 45 |
Investigation on irradiated-thermal-mechanical coupling performance and failure behaviors of TRISO particle fuel for space reactor applications
|
Peng, Lin
|
|
|
180 |
C |
p.
|
artikel
|
| 46 |
Investigations on fluid-induced vibrations of multi-row helical tube bundles in lead-bismuth eutectic flow with one-way coupling simulations
|
Yang, Guangchao
|
|
|
180 |
C |
p.
|
artikel
|
| 47 |
Irradiation-induced thermo-mechanical coupling method and deformation behaviors of hafnium control rod in the research reactor
|
Wang, Haoyu
|
|
|
180 |
C |
p.
|
artikel
|
| 48 |
MC/MOC two-step method for reactor physics analysis of helical cruciform fuel reactor
|
Song, Qufei
|
|
|
180 |
C |
p.
|
artikel
|
| 49 |
Mechanisms of crystalline swelling in bentonite buffer materials: Insights from molecular dynamics
|
Dai, Wen-jie
|
|
|
180 |
C |
p.
|
artikel
|
| 50 |
Modeling of the decomposition of iodine oxides aerosols (IOx) in the containment - Consequences on the understanding of volatile iodine behaviour in the containment
|
Bosland, L.
|
|
|
180 |
C |
p.
|
artikel
|
| 51 |
Multi-gene genetic programming of critical boron concentration and power peak factor for nuclear reactor fuel reload calculations
|
Filho, Marcos A.G.S.
|
|
|
180 |
C |
p.
|
artikel
|
| 52 |
Multivariate analysis quantifying amount of fissile isotopes for pebble-bed high temperature reactors
|
Zhang, Hongjian
|
|
|
180 |
C |
p.
|
artikel
|
| 53 |
Neighboring country's nuclear power plant? “No, thanks”: An energy justice analysis
|
Akyuz, Emrah
|
|
|
180 |
C |
p.
|
artikel
|
| 54 |
Neutronic analysis of Th-U molten salt reactor with FLiBe salt for different materials and geometry configurations
|
Yilmaz, Seda
|
|
|
180 |
C |
p.
|
artikel
|
| 55 |
Numerical & experimental study of single-phase flow in helically coiled pipes for laminar & turbulent regimes
|
Prakash, Alok
|
|
|
180 |
C |
p.
|
artikel
|
| 56 |
Numerical modeling, comprehensive energy-exergy-environmental (3E) analysis, and efficiency-based enhancement of the secondary circuit of the marine propulsion system: A case study of NS Savannah
|
Delgarm, Navid
|
|
|
180 |
C |
p.
|
artikel
|
| 57 |
Numerical research on the influence of inlet shape on the air flow and heat transfer characteristics inside the reactor channel
|
Zhao, Fulong
|
|
|
180 |
C |
p.
|
artikel
|
| 58 |
Numerical research on the thermal-hydraulic characteristics of the large sodium-cooled fast reactor roof slab
|
Zhang, Yuhao
|
|
|
180 |
C |
p.
|
artikel
|
| 59 |
Numerical safety analysis on a conceptual design of fluoride-salt-cooled high-temperature reactors under the influence of ocean conditions
|
Liu, Limin
|
|
|
180 |
C |
p.
|
artikel
|
| 60 |
Numerical simulation of condensate-induced water hammer with dynamic valve control using an advanced phase change model
|
Zhang, Zihao
|
|
|
180 |
C |
p.
|
artikel
|
| 61 |
Numerical simulation of flow field and metal deposition of Joule-heated ceramic melter for vitrification of radioactive waste
|
Ma, Yue
|
|
|
180 |
C |
p.
|
artikel
|
| 62 |
Numerical simulation study of liquid sodium contact angle on gradient sodium-philic nanostructure surface based on Lattice Boltzmann method for heat pipe rector application
|
Tang, Simiao
|
|
|
180 |
C |
p.
|
artikel
|
| 63 |
On the conception of pseudo-cross sections for neutron escape in physical Monte Carlo simulations in finite domains
|
Benvenutti, D.G.
|
|
|
180 |
C |
p.
|
artikel
|
| 64 |
Optimization and simulation of startup control for space nuclear power systems with closed brayton cycle based on NuHeXSys
|
Li, Chengyuan
|
|
|
180 |
C |
p.
|
artikel
|
| 65 |
Performance analysis and prediction of load bearing capacity of nuclear containment under overpressure and multi-hazard scenario
|
Fan, Qiaoqiao
|
|
|
180 |
C |
p.
|
artikel
|
| 66 |
Preliminary neutronics optimization on the concept of multi-beam accelerator driven system
|
Zhang, Xunchao
|
|
|
180 |
C |
p.
|
artikel
|
| 67 |
pyMAISE: A Python platform for automatic machine learning and accelerated development for nuclear power applications
|
Myers, Patrick A.
|
|
|
180 |
C |
p.
|
artikel
|
| 68 |
Quantitative comparison of explainable artificial intelligence methods for nuclear power plant accident diagnosis models
|
Kim, Seung Geun
|
|
|
180 |
C |
p.
|
artikel
|
| 69 |
Rational approximations for multi-energy group stiff fractional point kinetics equations
|
Aboanber, Ahmed E.
|
|
|
180 |
C |
p.
|
artikel
|
| 70 |
Reduced-order modeling of nonlinear flow-induced vibration of a loosely supported elastic tube via proper orthogonal decomposition
|
Zhao, Xielin
|
|
|
180 |
C |
p.
|
artikel
|
| 71 |
Reinforcement learning: Application to PWR's core power level control
|
Boubacar Kirgni, Hamza
|
|
|
180 |
C |
p.
|
artikel
|
| 72 |
Research on fluctuation attenuation and optimization of passive residual heat removal system based on spring vibrator
|
Wang, Sipeng
|
|
|
180 |
C |
p.
|
artikel
|
| 73 |
Research on multi-objective optimization design of the nuclear island cold chain system in HPR1000 based on a new hybrid genetic algorithm
|
Zhao, Weiguang
|
|
|
180 |
C |
p.
|
artikel
|
| 74 |
Scaling analysis of single-phase natural circulation in deep-pool-type nuclear heating reactors
|
Wang, Gongqing
|
|
|
180 |
C |
p.
|
artikel
|
| 75 |
Seismic performance of AP1000 nuclear power plants in earthquake-prone regions: A case study of the 2023 Türkiye earthquakes
|
Tandogan, Mesut
|
|
|
180 |
C |
p.
|
artikel
|
| 76 |
Study of oxide and α-Zr(O) growth kinetics in the temperature range 1000–1500 °C during steam oxidation of Indian PHWR cladding
|
Sawarn, Tapan K.
|
|
|
180 |
C |
p.
|
artikel
|
| 77 |
Study on bubble growth interphase heat transfer of rapid decompression
|
Deng, Jiewen
|
|
|
180 |
C |
p.
|
artikel
|
| 78 |
Study on coupled heat transfer characteristics and performance optimization for a helical coil heat exchanger in the lead-cooled fast reactor
|
Lei, Zhenxin
|
|
|
180 |
C |
p.
|
artikel
|
| 79 |
Study on internal flow characteristics of reactor coolant pump under non-uniform inflow
|
Long, Yun
|
|
|
180 |
C |
p.
|
artikel
|
| 80 |
The Lagrangian particle-based simulation of finned freeze plugs melting in the molten salt reactor
|
Hidayati, Anni Nuril
|
|
|
180 |
C |
p.
|
artikel
|
| 81 |
The neutronic analysis of heat pipe-cooled traveling wave reactors utilizing natural uranium
|
Hu, Po
|
|
|
180 |
C |
p.
|
artikel
|
| 82 |
Thermal-hydraulic analysis of <1–2> passes printed circuit heat exchanger with lead-bismuth and supercritical carbon dioxide as working fluids
|
Meng, Jia-tao
|
|
|
180 |
C |
p.
|
artikel
|
| 83 |
The social factors considered in site selection for nuclear power plants: A case study of Borneo Island, Indonesia
|
Abdullah, Ade Gafar
|
|
|
180 |
C |
p.
|
artikel
|
| 84 |
Upgrading the compressive strength and radiation shielding properties of high strength concrete supported with nano additives of lead monoxide and granodiorite
|
Fathy, Islam N.
|
|
|
180 |
C |
p.
|
artikel
|
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