| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A memory-efficient neutron noise algorithm for reactor physics
|
Cosgrove, Paul
|
|
|
201 |
C |
p.
|
artikel
|
| 2 |
An experimental study on the effect of coolant salinity on steam explosion
|
Deng, Yucheng
|
|
|
201 |
C |
p.
|
artikel
|
| 3 |
An improved parallel Random Sequential Addition algorithm in RMC code for dispersion fuel analysis
|
Tan, Zhe Chuan
|
|
|
201 |
C |
p.
|
artikel
|
| 4 |
A study on the roll compaction of dry concentrated waste liquid for disposal
|
Lim, Sang-Hyun
|
|
|
201 |
C |
p.
|
artikel
|
| 5 |
Bayesian update of fragility curves for equipment failure probability in seismic probabilistic safety assessment in nuclear power plant
|
Jiang, Hong
|
|
|
201 |
C |
p.
|
artikel
|
| 6 |
Conceptual study of a new space nuclear propulsion system based on direct propulsion of fission fragments
|
Zhang, Dacai
|
|
|
201 |
C |
p.
|
artikel
|
| 7 |
Development of coarse mesh finite difference acceleration in the three-dimensional discrete-ordinates discontinuous finite element transport code TARS
|
Zhang, Hu
|
|
|
201 |
C |
p.
|
artikel
|
| 8 |
Development of friction factor and heat transfer correlation of liquid metal flow in helical tube bundles
|
Shen, Cong
|
|
|
201 |
C |
p.
|
artikel
|
| 9 |
Editorial Board
|
|
|
|
201 |
C |
p.
|
artikel
|
| 10 |
Empirical model of flow-accelerated corrosion at elbow of carbon steel pipeline based on dimensional analysis
|
Bao, Guozhi
|
|
|
201 |
C |
p.
|
artikel
|
| 11 |
Enhancement in the safety and reliability of Pressurized Water reactors using Machine Learning approach
|
Zubair, Muhammad
|
|
|
201 |
C |
p.
|
artikel
|
| 12 |
Equivalent mechanical model for liquid sloshing in irregular annular cylindrical containers of liquid metal reactors
|
Zhu, Yuxuan
|
|
|
201 |
C |
p.
|
artikel
|
| 13 |
Evaluation of existing correlations and development of a new correlation for single-phase friction factor in rod bundle assembly
|
Chalgeri, Vikrant Siddharudh
|
|
|
201 |
C |
p.
|
artikel
|
| 14 |
Evaluation of probabilistic safety margin of nuclear power plant based on optimized adaptive sampling method
|
Chen, Haoyin
|
|
|
201 |
C |
p.
|
artikel
|
| 15 |
Experimental study of turbulent flow in lower plenum with flow skirt of reactor pressure vessel of pressurized water reactor
|
Qu, Wenhai
|
|
|
201 |
C |
p.
|
artikel
|
| 16 |
Forward and inverse predictive transient models of TREAT using surrogate reactivity models
|
Jaradat, Mustafa K.
|
|
|
201 |
C |
p.
|
artikel
|
| 17 |
Heaving motion effect on the transient thermodynamic characteristics of helical coil once-through steam generators in mixed ocean conditions
|
Zhang, Chao
|
|
|
201 |
C |
p.
|
artikel
|
| 18 |
Impact of the extended computational domain at inlet and outlet on natural convection in a vertical rectangular channel
|
Ji, Yongan
|
|
|
201 |
C |
p.
|
artikel
|
| 19 |
Intelligent multi-severity nuclear accident identification under transferable operation conditions
|
Xu, Song
|
|
|
201 |
C |
p.
|
artikel
|
| 20 |
Intelligent Radiation: A review of Machine learning applications in nuclear and radiological sciences
|
Jinia, Abbas J.
|
|
|
201 |
C |
p.
|
artikel
|
| 21 |
Investigation of the second-order nodal expansion method for the forward and adjoint neutron flux in the hexagonal geometry
|
Abbasi Fashami, Sajjad
|
|
|
201 |
C |
p.
|
artikel
|
| 22 |
Method of characteristics with a new Macro-track transport acceleration for complex general geometry
|
Jian, Guo
|
|
|
201 |
C |
p.
|
artikel
|
| 23 |
Model order reduction of a once-through steam generator via dynamic mode decomposition
|
Xu, Yifan
|
|
|
201 |
C |
p.
|
artikel
|
| 24 |
Multi-input and multi-output shielding calculation agent model method based on improved neural network with Swish-NNTA
|
Gui, Long
|
|
|
201 |
C |
p.
|
artikel
|
| 25 |
Next event estimation for neutron transport Monte Carlo simulations in moving objects
|
Zhang, Huayang
|
|
|
201 |
C |
p.
|
artikel
|
| 26 |
Novel polynomial Abet data augmentation algorithm with GRU paradigm for nuclear power prediction
|
Khan, Saifullah
|
|
|
201 |
C |
p.
|
artikel
|
| 27 |
Numerical simulation investigations on the flow induced vibration of a nuclear fuel rod with relaxed clamping structures
|
Jiao, Yongjun
|
|
|
201 |
C |
p.
|
artikel
|
| 28 |
Numerical simulation of typical abnormal operating conditions in the secondary circuit system of a Hua-long Pressurized Reactor nuclear power unit
|
Yang, Chen
|
|
|
201 |
C |
p.
|
artikel
|
| 29 |
Numerical simulation prediction of critical heat flux for 5 × 5 rod bundle with multiple grid spacers and different cladding materials
|
Liu, Kexin
|
|
|
201 |
C |
p.
|
artikel
|
| 30 |
Numerical study of mixing vane spacer grid effect on subchannel mixing in a 5 × 5 rod bundle
|
Qu, Wenhai
|
|
|
201 |
C |
p.
|
artikel
|
| 31 |
Numerical study of transient temperature thermal stress coupled heat transfer in spent fuel storage cask based on Gaussian random heat source
|
Cheng, Jianjie
|
|
|
201 |
C |
p.
|
artikel
|
| 32 |
Numerical study on flow instability of parallel helical tubes under convective heating condition
|
Liu, Maolong
|
|
|
201 |
C |
p.
|
artikel
|
| 33 |
Numerical study on surface corrosion deposition of fuel elements and its influence on flow heat transfer
|
Hou, Yandong
|
|
|
201 |
C |
p.
|
artikel
|
| 34 |
Research on protection control strategy of pressurized water reactor nuclear power units for typical power system faults
|
Wang, Haomin
|
|
|
201 |
C |
p.
|
artikel
|
| 35 |
Research on the flywheel clearance flow and heat transfer characteristics in a horizontal canned motor reactor coolant pump
|
Chen, Xiaohang
|
|
|
201 |
C |
p.
|
artikel
|
| 36 |
Sensitivity study of core characteristic parameter of ATF loaded APR1400 core and cycle length compensation by enrichment adjustment
|
Park, Kibeom
|
|
|
201 |
C |
p.
|
artikel
|
| 37 |
Small rotational fuel-shuffling breed-and-burn sodium-cooled and nitride-fueled fast reactor with LBE reflectors
|
Amarjargal, Tsendsuren
|
|
|
201 |
C |
p.
|
artikel
|
| 38 |
Spectrum features of the eigenvalue formulations in neutron transport
|
Abrate, Nicolò
|
|
|
201 |
C |
p.
|
artikel
|
| 39 |
Steady and transient solutions of neutron diffusion equations via computational methods based on Hartley series and higher order finite difference schemes
|
Hamada, Yasser Mohamed
|
|
|
201 |
C |
p.
|
artikel
|
| 40 |
Stochastic model updating for analysis of a nuclear containment vessel under internal pressure
|
Song, Meng-Yan
|
|
|
201 |
C |
p.
|
artikel
|
| 41 |
Study of microstructure and properties of SiCf/SiC-Zr composite cladding prepared through PIP
|
Meng, Ying
|
|
|
201 |
C |
p.
|
artikel
|
| 42 |
Study on flow regime prediction model for water-cooled reactor core based on machine learning algorithms
|
Ma, Yichao
|
|
|
201 |
C |
p.
|
artikel
|
| 43 |
Sub-modeling numerical analysis on the radionuclide release from a transport cask submerged in the deep sea
|
Jeong, Guhyeon
|
|
|
201 |
C |
p.
|
artikel
|
| 44 |
The impact of gamma-irradiation on physical properties and membrane distillation performance of PTFE and PVDF hollow fiber membrane
|
Jia, Xuxiang
|
|
|
201 |
C |
p.
|
artikel
|
| 45 |
Traditional machine learning methods in predicting the physics of subcritical systems in source-equilibrium
|
Gatchalian, Ronald Daryll E.
|
|
|
201 |
C |
p.
|
artikel
|
Tijdschrift beschrijving