| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A methodology for diagnosing FAC induced pipe thinning using accelerometers and deep learning models
|
Chae, Young Ho
|
|
|
143 |
C |
p.
|
artikel
|
| 2 |
Analysis of liquid droplet impacting on liquid film by CLSVOF
|
Chen, Bowen
|
|
|
143 |
C |
p.
|
artikel
|
| 3 |
Analysis of the multi-physics approach using the unified lattice Boltzmann framework
|
Wang, Yahui
|
|
|
143 |
C |
p.
|
artikel
|
| 4 |
A new generalized activation chain compression method in NECP-X
|
Liu, Zhouyu
|
|
|
143 |
C |
p.
|
artikel
|
| 5 |
A new method to determine conductivity distribution based on wire-mesh sensor by iteration
|
Zhang, Hengwei
|
|
|
143 |
C |
p.
|
artikel
|
| 6 |
Application of high-order numerical algorithm for two-fluid two-pressure model: Hydraulic load analysis
|
Zhang, Bin
|
|
|
143 |
C |
p.
|
artikel
|
| 7 |
Bundle geometry design influence on fuel burnup and performances in a CANDU reactor
|
Prodea, Iosif
|
|
|
143 |
C |
p.
|
artikel
|
| 8 |
Calculation of higher eigen-modes of the forward and adjoint neutron diffusion equations using IRAM algorithm based on domain decomposition
|
Wu, Wenbin
|
|
|
143 |
C |
p.
|
artikel
|
| 9 |
Design and optimization of Si-35S betavoltaic liquid nuclear battery in micro dimensions in order to build
|
Movahedian, Zohreh
|
|
|
143 |
C |
p.
|
artikel
|
| 10 |
Development of a dimensionless rod-bundle CHF correlation based on stepwise regression method, Part I: determination of the basic form with CHF data obtained with uniform axial heat flux profile
|
Pang, Bo
|
|
|
143 |
C |
p.
|
artikel
|
| 11 |
Development of an improved quasi-static transient analysis code based on three-dimensional Sn nodal transport theory for fast reactor
|
Takeda, Satoshi
|
|
|
143 |
C |
p.
|
artikel
|
| 12 |
Development of a versatile depletion code AMAC
|
Zhang, Binhang
|
|
|
143 |
C |
p.
|
artikel
|
| 13 |
Dynamic reliability framework for a Nuclear Power Plant using dynamic flowgraph methodology
|
Tripathi, Manish
|
|
|
143 |
C |
p.
|
artikel
|
| 14 |
Editorial Board
|
|
|
|
143 |
C |
p.
|
artikel
|
| 15 |
Effects of pH control agents on magnetite deposition on steam generator tubes
|
Lee, Ji-Min
|
|
|
143 |
C |
p.
|
artikel
|
| 16 |
Evaluation of improved subgroup resonance treatment based on Sanchez-Pomraning method for double heterogeneity in PWR
|
Li, Song
|
|
|
143 |
C |
p.
|
artikel
|
| 17 |
Experimental and computational investigations of gas entrainment in SFR due to rotation of partially submerged pump shaft
|
Khan, Faizan U.
|
|
|
143 |
C |
p.
|
artikel
|
| 18 |
Experimental investigation on split-mixing-vane forced mixing in pressurized water reactor fuel assembly
|
Xiong, Jinbiao
|
|
|
143 |
C |
p.
|
artikel
|
| 19 |
Experimental investigations on single-phase convection and critical heat flux in vertical tubes under oscillatory flow condition
|
Zhang, K.
|
|
|
143 |
C |
p.
|
artikel
|
| 20 |
Experimental study of the molten tin column impacting on the cooling water pool
|
Wang, Jiangtao
|
|
|
143 |
C |
p.
|
artikel
|
| 21 |
Experimental study on the effects of boiling during molten jet and coolant interactions
|
He, Longkun
|
|
|
143 |
C |
p.
|
artikel
|
| 22 |
Extended state observer-based adaptive dynamic sliding mode control for power level of nuclear power plant
|
Hui, Jiuwu
|
|
|
143 |
C |
p.
|
artikel
|
| 23 |
Flow boiling heat transfer under marine motions: A comprehensive review
|
Tian, Zhen
|
|
|
143 |
C |
p.
|
artikel
|
| 24 |
HGO-based adaptive super-twisting sliding mode power level control with prescribed performance for modular high-temperature gas-cooled reactors
|
Hui, Jiuwu
|
|
|
143 |
C |
p.
|
artikel
|
| 25 |
HTR-PM-based 3D pebble flow simulation on the effects of base angle, recirculation mode and coefficient of friction
|
Gui, Nan
|
|
|
143 |
C |
p.
|
artikel
|
| 26 |
Impact of magnetic structure and thermal effects on vibrational excitations and neutron scattering in uranium mononitride
|
Wormald, J.L.
|
|
|
143 |
C |
p.
|
artikel
|
| 27 |
Influence of graphitization degree of nuclear graphite on HTGR reactor physics calculation
|
Zhang, Lerui
|
|
|
143 |
C |
p.
|
artikel
|
| 28 |
Nuclear-data adjustment based on the continue-energy cross-section library for the fast reactor
|
Wan, Chenghui
|
|
|
143 |
C |
p.
|
artikel
|
| 29 |
Nuclear measurement in Pyro-processed wastes
|
Lee, YongDeok
|
|
|
143 |
C |
p.
|
artikel
|
| 30 |
Numerical investigation of the internally heated melt pool natural convection behavior with the consideration of different high internal Rayleigh numbers
|
Wei, Hongyang
|
|
|
143 |
C |
p.
|
artikel
|
| 31 |
Numerical investigation on Hopf bifurcation and post-instability of tube bundles subjected to two-phase cross-flow and loose support
|
Lai, Jiang
|
|
|
143 |
C |
p.
|
artikel
|
| 32 |
Numerical simulation of underwater air bubble formation under rolling conditions
|
Chen, Weixiong
|
|
|
143 |
C |
p.
|
artikel
|
| 33 |
Research on living PSA method based on time-dependent MFT for real-time online risk monitoring
|
Chen, Sijuan
|
|
|
143 |
C |
p.
|
artikel
|
| 34 |
RMC/CTF multiphysics solutions to VERA core physics benchmark problem #8
|
Luo, Zhen
|
|
|
143 |
C |
p.
|
artikel
|
| 35 |
Safety analysis of an advanced passively-cooled small modular reactor during station blackout scenarios and normal operation with RELAP5/SCDAP
|
Fakhraei, A.
|
|
|
143 |
C |
p.
|
artikel
|
| 36 |
Stability enhancement of planar transport solution based whole-core calculation employing augmented axial method of characteristics
|
Choi, Namjae
|
|
|
143 |
C |
p.
|
artikel
|
| 37 |
Stationarity Diagnostics using Functional Expansion Tallies
|
Kumar, Shikhar
|
|
|
143 |
C |
p.
|
artikel
|
| 38 |
The effects of minor actinide transmutation on PWR temperature coefficients
|
Liu, Bin
|
|
|
143 |
C |
p.
|
artikel
|
| 39 |
Thermal-hydraulic analysis of pellet bed reactor for space nuclear electric propulsion
|
Zhang, Ran
|
|
|
143 |
C |
p.
|
artikel
|
| 40 |
Time-space fractional neutron point kinetics: Theory and simulations
|
Espinosa-MartÃnez, E.-G.
|
|
|
143 |
C |
p.
|
artikel
|
| 41 |
Transient analysis of the Brazilian Multipurpose Reactor by the coupled neutronics and thermal hydraulics code NTHC1
|
Ribeiro, Eneida R.G.D.
|
|
|
143 |
C |
p.
|
artikel
|
| 42 |
Uncertainty and regression analysis of the MSLB accident in PWR based on unscented transformation and low rank approximation
|
Foad, Basma
|
|
|
143 |
C |
p.
|
artikel
|
| 43 |
Uncertainty quantification for TRACE simulation of FIX-II No. 5052 test
|
Chen, Yangli
|
|
|
143 |
C |
p.
|
artikel
|
| 44 |
Use of a success-oriented GO-FLOW method for system configuration risk management at NPPs
|
Yang, Jun
|
|
|
143 |
C |
p.
|
artikel
|
| 45 |
Whole-core analyses on recriticality of conventional high power pressurized water reactor in Korea during early phase of severe accidents
|
Lee, Yoonhee
|
|
|
143 |
C |
p.
|
artikel
|
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