| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A deep transfer learning method for system-level fault diagnosis of nuclear power plants under different power levels
|
Wang, Zhichao
|
|
|
166 |
C |
p.
|
artikel
|
| 2 |
A fuzzy-PID series feedback self-tuned adaptive control of reactor power using nonlinear multipoint kinetic model under reference tracking and disturbance rejection
|
Aftab, Adnan
|
|
|
166 |
C |
p.
|
artikel
|
| 3 |
A multiphase MPS method coupling fluid–solid interaction/phase-change models with application to debris remelting in reactor lower plenum
|
Duan, Guangtao
|
|
|
166 |
C |
p.
|
artikel
|
| 4 |
An efficient exponential representation for solving the two-energy group point telegraph kinetics model
|
Aboanber, Ahmed E.
|
|
|
166 |
C |
p.
|
artikel
|
| 5 |
A new method to simulate dispersion plate-type fuel assembly in a multi-physics coupled way
|
Xiang, Fengrui
|
|
|
166 |
C |
p.
|
artikel
|
| 6 |
An IFDF accelerated parallel nodal SN method for XYZ geometry in SARAX code system
|
Xu, Zhitao
|
|
|
166 |
C |
p.
|
artikel
|
| 7 |
An improved deterministic truncation of Monte Carlo solution for pin-resolved nuclear reactor analysis
|
Kim, Inhyung
|
|
|
166 |
C |
p.
|
artikel
|
| 8 |
A perturbation-based acceleration for Monte Carlo – Thermal Hydraulics Picard iterations. Part II: Application to 3D PWR-based problems
|
Terlizzi, Stefano
|
|
|
166 |
C |
p.
|
artikel
|
| 9 |
A physics-based parametric regression approach for feedwater pump system diagnosis
|
Nguyen, Tat Nghia
|
|
|
166 |
C |
p.
|
artikel
|
| 10 |
Application of G S P 3 ( 0 ) to anisotropic scattering case using the GTIN method
|
Li, Zhi-Yong
|
|
|
166 |
C |
p.
|
artikel
|
| 11 |
A propagation-based fault detection and discrimination method and the optimization of sensor deployment
|
Li, Boyuan
|
|
|
166 |
C |
p.
|
artikel
|
| 12 |
A quantitative accident analysis model on nuclear safety culture based on Bayesian network
|
Kim, Young Gab
|
|
|
166 |
C |
p.
|
artikel
|
| 13 |
Assessment of subchannel flow mixing coefficients for wire-wrapped hexagonal fuel rod bundles
|
Choi, Sun Rock
|
|
|
166 |
C |
p.
|
artikel
|
| 14 |
Conservation of natural Uranium by inter unit transfer of fuel in PHWRs
|
Bansal, Ravi Kumar
|
|
|
166 |
C |
p.
|
artikel
|
| 15 |
Design of Cesium target assembly with YH2 moderator and Gd thermal neutron shielding to produce 135Cs for LLFP transmutation study using the experimental fast reactor Joyo
|
Tahara, Yoshihisa
|
|
|
166 |
C |
p.
|
artikel
|
| 16 |
Detection and estimation of faulty sensors in NPPs based on thermal-hydraulic simulation and feed-forward neural network
|
Ebrahimzadeh, Alireza
|
|
|
166 |
C |
p.
|
artikel
|
| 17 |
Development and application of TaSNAM 2.0 for advanced pressurized water reactor
|
Huo, Yuchen
|
|
|
166 |
C |
p.
|
artikel
|
| 18 |
Development and implementation of a multi-physics high fidelity model of the TRIGA mark II reactor
|
Castagna, Christian
|
|
|
166 |
C |
p.
|
artikel
|
| 19 |
Development and validation of new algorithms for control rods insertion modeling in the RAPID code system using the JSI TRIGA Mark-II reactor
|
Mascolino, Valerio
|
|
|
166 |
C |
p.
|
artikel
|
| 20 |
Development of a cyberattack response planning method for nuclear power plants by using the Markov decision process model
|
Lee, Chanyoung
|
|
|
166 |
C |
p.
|
artikel
|
| 21 |
Development of a decision-making support system for the technical support center based on analysis of human performance under severe accident situation
|
Kang, Seongkeun
|
|
|
166 |
C |
p.
|
artikel
|
| 22 |
Development of code IMPC-MC1.0 by implementing the function for proton transport simulation in OpenMC
|
Zhao, Zelong
|
|
|
166 |
C |
p.
|
artikel
|
| 23 |
Development of NPP decommissioning cost estimation algorithm based on the CANDU structure
|
Kim, Minhee
|
|
|
166 |
C |
p.
|
artikel
|
| 24 |
Digital-twin-based improvements to diagnosis, prognosis, strategy assessment, and discrepancy checking in a nearly autonomous management and control system
|
Lin, Linyu
|
|
|
166 |
C |
p.
|
artikel
|
| 25 |
Distribution laws for radioisotopes in receiving freshwater of Inland Nuclear Power Plant
|
Wang, Jiaxin
|
|
|
166 |
C |
p.
|
artikel
|
| 26 |
Domain decomposition in the GPU-accelerated Shift Monte Carlo code
|
Hamilton, Steven P.
|
|
|
166 |
C |
p.
|
artikel
|
| 27 |
Dynamic characteristics of tube bundles with crack subjected to cross-flow and loose support
|
Lai, Jiang
|
|
|
166 |
C |
p.
|
artikel
|
| 28 |
Dynamic modeling and controlling of a spent nuclear fuel storage pool under periodic operation and station blackout conditions
|
Wahid, A.
|
|
|
166 |
C |
p.
|
artikel
|
| 29 |
Editorial Board
|
|
|
|
166 |
C |
p.
|
artikel
|
| 30 |
Effective multi-group cross section calculation method for FCM fuel based on improved disadvantage factor method
|
Yi, Siyu
|
|
|
166 |
C |
p.
|
artikel
|
| 31 |
Effect of impact velocity on time-dependent force and droplet pressure in high-speed liquid droplet impingement
|
Fujisawa, Kei
|
|
|
166 |
C |
p.
|
artikel
|
| 32 |
Evaluating attractiveness of cyberattack path using resistance concept and page-rank algorithm
|
Chae, Young Ho
|
|
|
166 |
C |
p.
|
artikel
|
| 33 |
Experimental and analytical determination of irradiated control rod worth of a low power research reactor
|
Ibrahim, Y.V.
|
|
|
166 |
C |
p.
|
artikel
|
| 34 |
Experimental investigation of natural convection and gas mixing behaviors driven by outer surface cooling with and without density stratification consisting of an air-helium gas mixture in a large-scale enclosed vessel
|
Abe, Satoshi
|
|
|
166 |
C |
p.
|
artikel
|
| 35 |
Experimental investigation of the pressure drop and friction factor of supercritical water in a 2 × 2 rod bundle
|
Wu, Gang
|
|
|
166 |
C |
p.
|
artikel
|
| 36 |
Experimental investigation of tube diameter and inclination angle on steam condensation accompanying with air in tube bundles
|
Cao, Boyang
|
|
|
166 |
C |
p.
|
artikel
|
| 37 |
Experimental research of nine parallel plane jets in non-blocking and blocking conditions
|
Wang, Peng
|
|
|
166 |
C |
p.
|
artikel
|
| 38 |
Experimental study of heat transfer in the complex space of small steel containment with a steam jet
|
Fang, Yuan
|
|
|
166 |
C |
p.
|
artikel
|
| 39 |
Flow induced vibration measurement for a 4 × 4 rod bundle with spacer grids by the Laser Doppler Vibrometer
|
Zhang, Botao
|
|
|
166 |
C |
p.
|
artikel
|
| 40 |
Impact of UF6 chemical toxicity on design and emergency response of a nuclear fuel fabrication facility in China
|
Ma, Qin-qin
|
|
|
166 |
C |
p.
|
artikel
|
| 41 |
Influence of crust formation on the heat load to a reactor vessel under an in-vessel retention condition
|
Park, Joon-Soo
|
|
|
166 |
C |
p.
|
artikel
|
| 42 |
Influence of thermal gradient and canister corrosion on the hydration of compacted Barmer bentonite
|
Kale, Rohini C.
|
|
|
166 |
C |
p.
|
artikel
|
| 43 |
Jacobian-free Newton Krylov nodal expansion method in three-dimensional cylindrical coordinates
|
Zhou, Xiafeng
|
|
|
166 |
C |
p.
|
artikel
|
| 44 |
lbmNTH: A unified lattice Boltzmann framework for coupled neutronics-thermal-hydraulics analysis
|
Wang, Yahui
|
|
|
166 |
C |
p.
|
artikel
|
| 45 |
Metaheuristic minimum dose path planning for nuclear power plant decommissioning
|
Lai, Ya-Ching
|
|
|
166 |
C |
p.
|
artikel
|
| 46 |
Methodology for an efficient statistical cross sections sampling in the unresolved resonance range
|
Jeannesson, C.
|
|
|
166 |
C |
p.
|
artikel
|
| 47 |
Model development and transient analysis of thermal stratification phenomenon in pool-type sodium-cooled fast reactors
|
Du, Peng
|
|
|
166 |
C |
p.
|
artikel
|
| 48 |
Multischeme equivalence procedure for neutron transport finite element methods
|
Labouré, Vincent
|
|
|
166 |
C |
p.
|
artikel
|
| 49 |
Neutronics/thermal-hydraulics/fuel-performance coupling for light water reactors and its application to accident tolerant fuel
|
Xu, Xiaobei
|
|
|
166 |
C |
p.
|
artikel
|
| 50 |
New basis functions for reactor core calculations using the nodal expansion method
|
Paixão, Sérgio B.
|
|
|
166 |
C |
p.
|
artikel
|
| 51 |
Nuclear emergency rescue drill database design and implementation
|
Cheng, Yuan
|
|
|
166 |
C |
p.
|
artikel
|
| 52 |
Numerical-analytical solutions of the fractional point kinetic model with Caputo derivatives
|
Polo-Labarrios, M.A.
|
|
|
166 |
C |
p.
|
artikel
|
| 53 |
Numerical simulation of two-dimensional fractional neutron diffusion model describing dynamical behaviour of sodium-cooled fast reactor
|
Roul, Pradip
|
|
|
166 |
C |
p.
|
artikel
|
| 54 |
ODR-VS method for a high packing fraction of dispersed TRISO particles
|
Feng, Zhiyuan
|
|
|
166 |
C |
p.
|
artikel
|
| 55 |
Operation and safety analysis of space lithium-cooled fast nuclear reactor
|
Jin, Zhao
|
|
|
166 |
C |
p.
|
artikel
|
| 56 |
Prediction of safety parameters of pressurized water reactor based on feature fusion neural network
|
Chen, Yinghao
|
|
|
166 |
C |
p.
|
artikel
|
| 57 |
Prediction of steam/water stratified flow characteristics in NPPs transients using SVM learning algorithm with combination of thermal-hydraulic model and new data mapping technique
|
Moshkbar-Bakhshayesh, Khalil
|
|
|
166 |
C |
p.
|
artikel
|
| 58 |
Preliminary assessment of the impact of extrapolation distance on the results of Time-Average calculations in CANDU analyses
|
Kastanya, Doddy
|
|
|
166 |
C |
p.
|
artikel
|
| 59 |
Quantum evolutionary algorithm based power optimization control strategy for China initiative accelerator driven subcritical system
|
Li, Jin-Yang
|
|
|
166 |
C |
p.
|
artikel
|
| 60 |
Reactor pressure vessel damage (dpa/s) calculation and testing of 56Fe data libraries based on PCA benchmark model simulations using the SuperMC 3.4 code
|
Baidoo, I.K.
|
|
|
166 |
C |
p.
|
artikel
|
| 61 |
Relationship between Tone’s method and embedded self-shielding method
|
Rao, Junjie
|
|
|
166 |
C |
p.
|
artikel
|
| 62 |
Reliability analysis and safety model checking of Safety-Critical and control Systems: A case study of NPP control system
|
Kumar, Vinay
|
|
|
166 |
C |
p.
|
artikel
|
| 63 |
Researches on thermal hydraulics and fuel performance of ATFs during extreme steam generator tube failure without ECCS and DHRS in NuScale
|
Yu, Honghao
|
|
|
166 |
C |
p.
|
artikel
|
| 64 |
Research on multi-electrode capacitance rod position measurement sensor for NHR-200
|
Li, Yanlin
|
|
|
166 |
C |
p.
|
artikel
|
| 65 |
Risk modelling of ageing nuclear reactor systems
|
Wootton, Mark James
|
|
|
166 |
C |
p.
|
artikel
|
| 66 |
Selection methodology of the optimal cutting technology for dismantling of components in nuclear power plants
|
Lee, Ga-Ram
|
|
|
166 |
C |
p.
|
artikel
|
| 67 |
Sensitivity study of thermal-hydraulic nodalization for MELCOR simulations of severe accidents in a pressurized water reactor
|
Zhao, Nan
|
|
|
166 |
C |
p.
|
artikel
|
| 68 |
Source extrapolation scheme for Monte Carlo fission source convergence based on RMC code
|
Pan, Qingquan
|
|
|
166 |
C |
p.
|
artikel
|
| 69 |
Spatial convergence study of Lax-Friedrichs WENO fast sweeping method on the SN transport equation with nonsmoothness
|
Zhou, Shengcheng
|
|
|
166 |
C |
p.
|
artikel
|
| 70 |
Study on neutron shielding performance of hot cell shielding door for nuclear power plant
|
Zhang, Shanwen
|
|
|
166 |
C |
p.
|
artikel
|
| 71 |
Sub-space iteration based Monte Carlo scheme for simultaneous computation of multiple dominant k-eigenmodes and acceleration of fission source iterations
|
Mallick, Amod Kishore
|
|
|
166 |
C |
p.
|
artikel
|
| 72 |
Technological solutions for long-term storage of partially used nuclear waste: A critical review
|
Kurniawan, Tonni Agustiono
|
|
|
166 |
C |
p.
|
artikel
|
| 73 |
The development of fuel management code TRACS for HFETR based on Unstructured-mesh variational nodal method
|
Zhuang, Kun
|
|
|
166 |
C |
p.
|
artikel
|
| 74 |
Thermo-chemical behavior of PHWR disassembled channel during severe accident condition: Numerical and experimental investigation
|
Kumar, Rohit
|
|
|
166 |
C |
p.
|
artikel
|
| 75 |
Transfer function modeling and simulation of HPR1000
|
Zhang, Xianshan
|
|
|
166 |
C |
p.
|
artikel
|
| 76 |
Uncertainty quantification study on gas phase iodine release from Fukushima Daiichi accident in unit 3
|
Kalilainen, Jarmo
|
|
|
166 |
C |
p.
|
artikel
|
| 77 |
Utilization of PARCS/Serpent in small-scale reactor – Multiplication factor, rod worth, and transient
|
Fejt, F.
|
|
|
166 |
C |
p.
|
artikel
|
| 78 |
Verification of multi-group cross-section generation code ARES-MACXS with fusion neutron shielding benchmark OKTAVIAN-Fe
|
Hu, Jiaju
|
|
|
166 |
C |
p.
|
artikel
|
| 79 |
Verification of the code DYN3D for calculations of neutron flux fluctuations
|
Viebach, M.
|
|
|
166 |
C |
p.
|
artikel
|
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