| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A comprehensive review of experimental and numerical studies on liquid metal-gas two-phase flows and associated measurement challenges
|
Saraswat, Abhishek
|
|
|
213 |
C |
p.
|
artikel
|
| 2 |
A fault diagnosis method for rotating machinery in nuclear power plants based on long short-term memory and temporal convolutional networks
|
Wang, Pengfei
|
|
|
213 |
C |
p.
|
artikel
|
| 3 |
A heterogeneous robot collaborative search method for radioactive sources
|
Ling, Ming-Run
|
|
|
213 |
C |
p.
|
artikel
|
| 4 |
Analysis of the modal characteristics of NHR200-II fuel rods in turbulent axial flow
|
Lin, Musen
|
|
|
213 |
C |
p.
|
artikel
|
| 5 |
A new and rigorous SPN theory – The concluding Part V: Completion of the numerical solution method for GSP3 equations
|
Chao, Yung-An
|
|
|
213 |
C |
p.
|
artikel
|
| 6 |
An improved model of pressure drops in gas–water two-phase flow through packed debris beds for wide void fraction
|
Zou, Wenbin
|
|
|
213 |
C |
p.
|
artikel
|
| 7 |
A non-parametric bootstrap method for Monte Carlo neutron transport
|
Skretteberg, Martin
|
|
|
213 |
C |
p.
|
artikel
|
| 8 |
A novel node collocation technique in radial basis function collocation method applied to neutron diffusion equations
|
Luo, Yiyang
|
|
|
213 |
C |
p.
|
artikel
|
| 9 |
Application of machine learning to predict safeguards parameters for irradiated salts from a molten salt reactor concept
|
Mishra, Vaibhav
|
|
|
213 |
C |
p.
|
artikel
|
| 10 |
A preliminary study on the blistering behavior of dispersion plate-type fuel assembly
|
Yu, Songjiao
|
|
|
213 |
C |
p.
|
artikel
|
| 11 |
A robust diagnosis method specifically for similar faults in nuclear power plant multi-systems based on data segmentation and stacked convolutional autoencoders
|
Ai, Xin
|
|
|
213 |
C |
p.
|
artikel
|
| 12 |
Artificial intelligence-driven advances in nuclear technology: Exploring innovations, applications, and future prospects
|
Arhouni, Fatima Ezzahra
|
|
|
213 |
C |
p.
|
artikel
|
| 13 |
Assessment of flow mixing in ROCOM reactor using TRACE5 and CFD
|
Messiga, Juan P.
|
|
|
213 |
C |
p.
|
artikel
|
| 14 |
Automated control for nuclear thermal propulsion transient phases using point kinetics-based power balance modeling
|
Ghossein, Anthony Y.
|
|
|
213 |
C |
p.
|
artikel
|
| 15 |
Bidirectional transmutation method for optimal reactor radionuclide production
|
Li, Dongyuan
|
|
|
213 |
C |
p.
|
artikel
|
| 16 |
Calculation of adjoint flux in the lattice code PINE and validation on neutron kinetics parameters
|
Liang, Jiali
|
|
|
213 |
C |
p.
|
artikel
|
| 17 |
CFD simulation of injection point design for emergency core cooling system of ALLEGRO
|
Ding, C.
|
|
|
213 |
C |
p.
|
artikel
|
| 18 |
Comprehensive study on parameter sensitivity analysis of steam reformer tube for hydrogen production using HTGR
|
Wu, Chengye
|
|
|
213 |
C |
p.
|
artikel
|
| 19 |
Coolant contamination in gas-cooled reactors due to neutronic sputtering
|
Chiovaro, P.
|
|
|
213 |
C |
p.
|
artikel
|
| 20 |
Coupled simulation for pin-wise reactor core analysis using subchannel analysis code CUPID and fuel performance code GIFT
|
Lee, Yeong Hun
|
|
|
213 |
C |
p.
|
artikel
|
| 21 |
Coupled STH/CFD calculations in support of the upcoming CIRCE-THETIS Experimental Campaign
|
Stefanini, Pietro
|
|
|
213 |
C |
p.
|
artikel
|
| 22 |
Criticality analysis of the optimum moderation condition in the PWR fuel storage Facility
|
Park, Dong Hyeok
|
|
|
213 |
C |
p.
|
artikel
|
| 23 |
Design and optimization of average coolant temperature control system for the small lead–bismuth fast reactor
|
Zhang, Ru
|
|
|
213 |
C |
p.
|
artikel
|
| 24 |
Design evaluation of serpentine-tube integrated steam generator for sodium-cooled fast reactor
|
Lee, Jewhan
|
|
|
213 |
C |
p.
|
artikel
|
| 25 |
Design of a 24-month equilibrium cycle of a BWR with extended low enrichment fuel using metaheuristic optimization techniques
|
López-Luna, Javier
|
|
|
213 |
C |
p.
|
artikel
|
| 26 |
Design of open-tank-in-pool-type educational critical assemblies using UO2 and U-7Mo fuels
|
Song, Kyoseong
|
|
|
213 |
C |
p.
|
artikel
|
| 27 |
Development and application of a multi-scale Thermal-Hydraulic coupling program for whole-core flow blockage analysis
|
Luo, Xiao
|
|
|
213 |
C |
p.
|
artikel
|
| 28 |
Development and verification of the multi-group covariance processing code CovarXS
|
LIU, Sha
|
|
|
213 |
C |
p.
|
artikel
|
| 29 |
Development of a two-phase flow solver with drift-flux model based on OpenFOAM: Validation against single/two-phase and boiling flow
|
Wu, Wenqiang
|
|
|
213 |
C |
p.
|
artikel
|
| 30 |
Development of CNN-Based surrogate models to predict power distributions in i-SMR
|
Kwon, Jungseok
|
|
|
213 |
C |
p.
|
artikel
|
| 31 |
Editorial Board
|
|
|
|
213 |
C |
p.
|
artikel
|
| 32 |
Effects of components’ arrangement on the sloshing behavior inside liquid metal reactors under seismic excitation
|
Chen, Yalou
|
|
|
213 |
C |
p.
|
artikel
|
| 33 |
Energy-dependent neutron removal cross-section
|
Soliman, A.
|
|
|
213 |
C |
p.
|
artikel
|
| 34 |
Evaluation of the structural and radiation transmission parameters of recycled borosilicate waste glass system: An effective material for nuclear shielding
|
Al-Buriahi, M.S.
|
|
|
213 |
C |
p.
|
artikel
|
| 35 |
Experimental research on thermal transient flow characteristics of control rod hydraulic drive system
|
Qin, Benke
|
|
|
213 |
C |
p.
|
artikel
|
| 36 |
Experimental simulation of under sodium ultrasonic imaging in a sodium cooled fast breeder reactor using a scaled down model of the core
|
Patel, Deepak
|
|
|
213 |
C |
p.
|
artikel
|
| 37 |
Experimental study on the CHF of IVR-ERVC system with an elliptical lower head under forced circulation condition
|
Kuang, Bo
|
|
|
213 |
C |
p.
|
artikel
|
| 38 |
Homogeneity and isotropy restoration (HIRE)-Theoretic multigroup neutron transport equations and Two-Level p-CMFD acceleration scheme
|
Cho, Nam Zin
|
|
|
213 |
C |
p.
|
artikel
|
| 39 |
Influence mechanism of the non-uniform inflow on flow characteristics of horizontal reactor coolant pump
|
Lu, Jinqi
|
|
|
213 |
C |
p.
|
artikel
|
| 40 |
Letter to editor: Utilizing artificial neural networks to convert gamma-ray spectra from NaI(Tl) detectors to HPGe detector gamma-ray spectra
|
Kafaee, Mahdi
|
|
|
213 |
C |
p.
|
artikel
|
| 41 |
Loss of coolant accident diagnosis for large pressurized water reactors based on long short-term memory network
|
Zhu, Ze
|
|
|
213 |
C |
p.
|
artikel
|
| 42 |
Machine learning approach for predicting nuclide composition in nuclear fuel: Bypassing traditional depletion and transport calculations
|
Chan, Yi Meng
|
|
|
213 |
C |
p.
|
artikel
|
| 43 |
Measurement and calculation of the void reactivity coefficient of the Jordan research and training reactor (JRTR)
|
Kim, Kyung-O
|
|
|
213 |
C |
p.
|
artikel
|
| 44 |
Modification to aerosols dispersion algorithms over two-dimensional hilly terrain based on wind tunnel atmospheric experiments
|
Wu, Siyuan
|
|
|
213 |
C |
p.
|
artikel
|
| 45 |
Monte Carlo methods based on “virtual density” theory for calculation of k-eigenvalue sensitivity under nonuniform anisotropic deformation
|
Yamamoto, Toshihiro
|
|
|
213 |
C |
p.
|
artikel
|
| 46 |
Neutronics analysis of the spatial separation of fuel in lithium cooled space fast reactors
|
Wang, Yue
|
|
|
213 |
C |
p.
|
artikel
|
| 47 |
Numerical analysis on redistribution performance of typical flow distribution devices of RPV under ocean condition
|
Ruan, Haoyu
|
|
|
213 |
C |
p.
|
artikel
|
| 48 |
Numerical investigation of gas–liquid two-phase flow in a U-tube of a spray cooling system
|
Zhang, Haijun
|
|
|
213 |
C |
p.
|
artikel
|
| 49 |
Numerical investigation of impurity deposition and filtration characteristics for lead-bismuth eutectic cooled system
|
Pang, Xiao
|
|
|
213 |
C |
p.
|
artikel
|
| 50 |
Numerical Investigation on molten Lead–Bismuth Eutectic solidification characteristics outside vertical tube bundles
|
Zhu, Mengyu
|
|
|
213 |
C |
p.
|
artikel
|
| 51 |
Numerical simulation of bubble migration characteristics and distribution probability under lead-cooled fast reactor during SGTR accident
|
Luo, Haotian
|
|
|
213 |
C |
p.
|
artikel
|
| 52 |
On the Intermediary Resonance method and beyond
|
Sanchez, Richard
|
|
|
213 |
C |
p.
|
artikel
|
| 53 |
On the ionizing radiation protection properties of different chromium-based alloys: A study with the Geant4 Monte Carlo toolkit
|
Hamad, Morad Kh.
|
|
|
213 |
C |
p.
|
artikel
|
| 54 |
Performance of potentiometric oxygen sensors with LSM composite electrode in saturated oxygen liquid LBE
|
Li, Hui
|
|
|
213 |
C |
p.
|
artikel
|
| 55 |
P1 generalized equivalence theory for PWR-core pin-by-pin neutronics calculation
|
Qin, Junwei
|
|
|
213 |
C |
p.
|
artikel
|
| 56 |
Preliminary thermal-hydraulic safety analysis of the 600 thermal megawatt dual fluid reactor
|
Arnold, B.
|
|
|
213 |
C |
p.
|
artikel
|
| 57 |
Problem analysis and new scheme design for AB-BNCT solid Li targets
|
Qin, Kaiwen
|
|
|
213 |
C |
p.
|
artikel
|
| 58 |
Proposition of a small molten salt modular reactor utilizing fine-mesh 1:1 coupled calculations—Part I
|
Vieira, Tiago Augusto Santiago
|
|
|
213 |
C |
p.
|
artikel
|
| 59 |
Redesign, construction and commissioning of a powder neutron diffractometer in Tehran research reactor
|
Bavarnegin, E.
|
|
|
213 |
C |
p.
|
artikel
|
| 60 |
Reduced-order modeling of neutron transport separated in axial and radial space by Proper Generalized Decomposition with applications to nuclear reactor physics
|
Dominesey, Kurt A.
|
|
|
213 |
C |
p.
|
artikel
|
| 61 |
Research and Validation of the Monte Carlo-based multi-cycle neutronic Simulations methodology for HFETR
|
Xia, Yi
|
|
|
213 |
C |
p.
|
artikel
|
| 62 |
Research on an intelligent fault diagnosis method for nuclear power plants based on ETCN-SSA combined algorithm
|
Fang, Jiayan
|
|
|
213 |
C |
p.
|
artikel
|
| 63 |
Research on fault diagnosis method and interpretability of nuclear power plant based on hybrid transformer model
|
Zhou, Gui
|
|
|
213 |
C |
p.
|
artikel
|
| 64 |
Research on flow characteristics of reactor coolant pumps under non-uniform inflow
|
Long, Yun
|
|
|
213 |
C |
p.
|
artikel
|
| 65 |
Research on least-square solver for physics-informed neural network in thermal-hydraulic analysis of nuclear reactors
|
Bo, Wang
|
|
|
213 |
C |
p.
|
artikel
|
| 66 |
Research on reactor core pin-by-pin calculation based on new leakage corrected SPH method
|
Wang, Xiaoyu
|
|
|
213 |
C |
p.
|
artikel
|
| 67 |
Review on the fuel management strategy of the RSG-GAS equilibrium core
|
Pinem, Surian
|
|
|
213 |
C |
p.
|
artikel
|
| 68 |
Semi-automatic image annotation using 3D LiDAR projections and depth camera data
|
Li, Pei Yao
|
|
|
213 |
C |
p.
|
artikel
|
| 69 |
Spot versus gap conductance, and interfacial heat transfer between the pressure-tube and calandria-tube of Indian PHWR
|
Chand, Arun
|
|
|
213 |
C |
p.
|
artikel
|
| 70 |
Statistical and theoretical analysis of iodine spiking phenomena during steam generator tube rupture
|
Lu, Changdong
|
|
|
213 |
C |
p.
|
artikel
|
| 71 |
Study on in-vessel injection strategy for IVR improvement
|
Mingguang, Zheng
|
|
|
213 |
C |
p.
|
artikel
|
| 72 |
Study on permeability from 3D images of nuclear grade graphite IG-110 by the multidimensional capillary bundle model, lattice Boltzmann method and experiment
|
Peng, Lei
|
|
|
213 |
C |
p.
|
artikel
|
| 73 |
Study on the characteristics of gas-liquid two-phase flow with forward-rotation in reactor coolant pump under LOCA
|
Li, Huairui
|
|
|
213 |
C |
p.
|
artikel
|
| 74 |
Study on the flow and heat transfer of LBE in wire-rod and rib-rod bundle channels
|
Dong, Xianmin
|
|
|
213 |
C |
p.
|
artikel
|
| 75 |
Systematic formula of pre-neutron-emission mass distributions for neutron-induced actinide fission at low incident energies
|
Zou, Fanglei
|
|
|
213 |
C |
p.
|
artikel
|
| 76 |
Temperature flattening and thermoelectric conversion modeling of TOPAZ-II thermionic reactor
|
Wu, Yao
|
|
|
213 |
C |
p.
|
artikel
|
| 77 |
Testing and implementation of LEU+ 6% enriched UO2 fuel at The PULSTAR reactor
|
Fleming, N.C.
|
|
|
213 |
C |
p.
|
artikel
|
| 78 |
The AGN-201 Digital Twin: A test bed for remotely monitoring nuclear reactors
|
Stewart, Ryan
|
|
|
213 |
C |
p.
|
artikel
|
| 79 |
The optimization of phase change heat transfer model for direct contact condensation heat transfer simulation based on Bayesian inversion method
|
Wang, Yiwei
|
|
|
213 |
C |
p.
|
artikel
|
| 80 |
The passive heat removal facility (PHRF) and its first phase experiments
|
Liao, Jun
|
|
|
213 |
C |
p.
|
artikel
|
| 81 |
Thermal safety analysis of thermionic space nuclear reactor startup on orbit
|
Jin, Zhao
|
|
|
213 |
C |
p.
|
artikel
|
| 82 |
The two point Feynman- α theory: Theory and practice of Ex-Core reactor noise measurement
|
Dubi, C.
|
|
|
213 |
C |
p.
|
artikel
|
| 83 |
Topology optimization analysis on mixing vane of spacer grid in reactor core
|
Wang, Sipeng
|
|
|
213 |
C |
p.
|
artikel
|
| 84 |
Towards high-fidelity high-resolution modeling of a BWR fuel assembly by CASMO-5
|
Cherezov, Alexey
|
|
|
213 |
C |
p.
|
artikel
|
| 85 |
TRACE system code benchmark of Station Blackout of a NuScale-like reactor and comparison with NuScale simulator
|
Gorman, Michael
|
|
|
213 |
C |
p.
|
artikel
|
| 86 |
Transient analysis of target loading in neutron flux trap channel of Tehran research reactor compact core
|
Safaei Arshi, S.
|
|
|
213 |
C |
p.
|
artikel
|
| 87 |
Turbulent random loads on wire wrapped fuel rod bundle: theory, simulations and formulas
|
Zhang, Yu
|
|
|
213 |
C |
p.
|
artikel
|
| 88 |
Uncertainty quantification in Bayesian inverse problems with neutron and gamma time correlation measurements
|
Lartaud, Paul
|
|
|
213 |
C |
p.
|
artikel
|
| 89 |
Verification of reduced-order model subspace dimensions and minimal ranks in simple configurations
|
Ragusa, Jean C.
|
|
|
213 |
C |
p.
|
artikel
|
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