| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
ADS design concept for disposing of the U.S. spent nuclear fuel inventory
|
Gohar, Yousry
|
|
|
160 |
C |
p.
|
artikel
|
| 2 |
A dynamic homogenization method for 3D core calculations
|
Galia, Antonio
|
|
|
160 |
C |
p.
|
artikel
|
| 3 |
A hash mapping method using cell vectors in Monte Carlo code RMC
|
Guo, Xiaoyu
|
|
|
160 |
C |
p.
|
artikel
|
| 4 |
Ameliorating the positive temperature feedback coefficient for an MSR fueled with transuranic elements
|
Zou, Chunyan
|
|
|
160 |
C |
p.
|
artikel
|
| 5 |
Analysis for the ARIANE GU1 sample: Nuclide inventory and decay heat
|
Rochman, D.
|
|
|
160 |
C |
p.
|
artikel
|
| 6 |
Analysis of concrete ablation depth by MCCI assuming top flooding condition of APR1400 NPP
|
Na, Hanbee
|
|
|
160 |
C |
p.
|
artikel
|
| 7 |
A network approach to full core temperature analysis in advanced nuclear heat-pipe systems
|
Mueller, Cole
|
|
|
160 |
C |
p.
|
artikel
|
| 8 |
A nodal sensitivity study of MELCOR simulation for severe accidents in a pressurized water reactor
|
Zhao, Nan
|
|
|
160 |
C |
p.
|
artikel
|
| 9 |
A novel method for the design and selection of neutron-attenuating media
|
Weiss, Abdullah G.
|
|
|
160 |
C |
p.
|
artikel
|
| 10 |
A review of heat-pipe modeling and simulation approaches in nuclear systems design and analysis
|
Mueller, Cole
|
|
|
160 |
C |
p.
|
artikel
|
| 11 |
A study on steam cycle optimization for integrating energy storage system to nuclear power plant
|
Lee, Ju Yeon
|
|
|
160 |
C |
p.
|
artikel
|
| 12 |
Augmented ENDF/B-VIII.0 covariance library for SCALE 6.3
|
Sobes, Vladimir
|
|
|
160 |
C |
p.
|
artikel
|
| 13 |
Automatic differentiation approach for solving one-dimensional flow and heat transfer problems
|
Niu, Yuhang
|
|
|
160 |
C |
p.
|
artikel
|
| 14 |
Best-practice severe accident analysis for the OPR1000 short-term SBO sequence using MELCOR2.2 and MAAP5
|
Ahn, Kwang-Il
|
|
|
160 |
C |
p.
|
artikel
|
| 15 |
Burn-cycle-dependent spatial distribution of nuclear fuel actinides and fission products based on the AGENT code
|
Saenz, Brittney L.
|
|
|
160 |
C |
p.
|
artikel
|
| 16 |
Classification of group structures for a multigroup collision probability model using machine learning
|
Berry, Jessica J.
|
|
|
160 |
C |
p.
|
artikel
|
| 17 |
Code development and analysis on the operation of liquid metal high temperature heat pipes under full condition
|
Tian, Zhixing
|
|
|
160 |
C |
p.
|
artikel
|
| 18 |
Convergence study of CMFD based acceleration schemes for multi-group transport calculations with fission source using fourier analysis
|
Jain, Lakshay
|
|
|
160 |
C |
p.
|
artikel
|
| 19 |
Corrigendum to: Investigations of the fresh-core cycle-length and the average fuel depletion analysis of the NuScale core [ANE, Volume 136,February 2020, 106995]
|
Dast-belaraki, M.A.
|
|
|
160 |
C |
p.
|
artikel
|
| 20 |
Critical heat flux measurement and visualization in R-134a on a vertical single rod with and without mixing-vanes spacer: The characteristics and phenomenon of critical heat flux
|
Liu, Yang
|
|
|
160 |
C |
p.
|
artikel
|
| 21 |
Design of temperature controlled instrumented irradiation capsule for irradiation experiments in FBTR
|
Saurav, Suman
|
|
|
160 |
C |
p.
|
artikel
|
| 22 |
Developing a method for time-variant reliability assessment of passive heat removal systems in nuclear power plants
|
Ebrahimian, M.
|
|
|
160 |
C |
p.
|
artikel
|
| 23 |
Development and validation of PROTEUS-NODAL transient analyses capabilities for molten salt reactors
|
Jaradat, Mustafa K.
|
|
|
160 |
C |
p.
|
artikel
|
| 24 |
Development of a flow sweeping mixing model for helical fuel rod bundles
|
Xiao, Yao
|
|
|
160 |
C |
p.
|
artikel
|
| 25 |
Development of a transient module based on FROBA-ROD code and assessment for fuel rod performance under reactivity-initiated accident
|
Liao, Haoyu
|
|
|
160 |
C |
p.
|
artikel
|
| 26 |
Editorial Board
|
|
|
|
160 |
C |
p.
|
artikel
|
| 27 |
Effectiveness of the ASVAD valve in a reactor vessel bottom leak scenario
|
Freixa, Jordi
|
|
|
160 |
C |
p.
|
artikel
|
| 28 |
Effects of edge geometry on the flow-induced acoustic resonances in closed side branches
|
Xiao, Yao
|
|
|
160 |
C |
p.
|
artikel
|
| 29 |
Estimation of the fuel debris thermal energy at the time of the major core slumping of Fukushima Daiichi Nuclear Power Plant Unit-3 with MELCOR-2.2
|
Regalado, Mariko
|
|
|
160 |
C |
p.
|
artikel
|
| 30 |
Experimental study on gas mixing and transport induced by external cooling on large-scale facility
|
Li, Y.
|
|
|
160 |
C |
p.
|
artikel
|
| 31 |
Experimental study on thermo-chemical behavior of PHWR fuel channel under slumped fuel pin condition
|
Ajay, Ketan
|
|
|
160 |
C |
p.
|
artikel
|
| 32 |
Experimental study on treatment of simulated radioactive waste by thermal plasma: Temporal evaluation of stable Co and Cs
|
Prado, E.S.P.
|
|
|
160 |
C |
p.
|
artikel
|
| 33 |
Feature extraction for early fault detection in rotating machinery of nuclear power plants based on adaptive VMD and Teager energy operator
|
Zhu, Shaomin
|
|
|
160 |
C |
p.
|
artikel
|
| 34 |
Improvements of RELAP5/Mod3.3 heat transfer capabilities for simulation of in-pool passive power removal systems
|
Narcisi, Vincenzo
|
|
|
160 |
C |
p.
|
artikel
|
| 35 |
Influence of coupled factors on premixing and fragmentation of mild thermal interaction
|
Peng, Cheng.
|
|
|
160 |
C |
p.
|
artikel
|
| 36 |
In-situ demonstration of engineered barrier system (In-DEBS) at KURT: Coupled thermal-hydro-mechanical behavior of buffer
|
Lee, Jae Owan
|
|
|
160 |
C |
p.
|
artikel
|
| 37 |
Investigation of fluid-structure Interaction of fuel element in high speed and high temperature air cooled reactor
|
Lu, Ruibo
|
|
|
160 |
C |
p.
|
artikel
|
| 38 |
Large-scale design optimisation of boiling water reactor bundles with neuroevolution
|
Radaideh, Majdi I.
|
|
|
160 |
C |
p.
|
artikel
|
| 39 |
Lie group analysis of the point-reactor neutron kinetics equations for various reactivity models
|
O’Rourke, Patrick F.
|
|
|
160 |
C |
p.
|
artikel
|
| 40 |
Multi-objective optimization method for nuclear reactor radiation shielding design based on PSO algorithm
|
Wu, Xiang
|
|
|
160 |
C |
p.
|
artikel
|
| 41 |
Neutronic analysis of VVER-1000 MOX fuel assembly with burnable absorber Gadolinia and Erbia
|
Ovi, Mahmud Hasan
|
|
|
160 |
C |
p.
|
artikel
|
| 42 |
Novel solution to the fractional neutron point kinetic equation using conformable derivatives
|
Fernández-Anaya, G.
|
|
|
160 |
C |
p.
|
artikel
|
| 43 |
Numerical simulation on transient thermal and hydraulic characteristics in sodium pool of CEFR under OPT-SLOOP and OPT-RHROSL conditions
|
Liang, Jiangtao
|
|
|
160 |
C |
p.
|
artikel
|
| 44 |
Numerical studies on bubble dynamics in an unsteady turbulence of the venturi bubble generator applied to TMSR
|
Song, Yuchen
|
|
|
160 |
C |
p.
|
artikel
|
| 45 |
On the Response Matrix–Constant Nodal method applied to S N problems with arbitrary L’th-order anisotropic scattering
|
Curbelo, Jesús P.
|
|
|
160 |
C |
p.
|
artikel
|
| 46 |
Primary coolant activity of 54Mn, 59Fe, 58Co, 60Co, and 51Cr in system integrated small and modular reactor
|
Mehboob, Khurram
|
|
|
160 |
C |
p.
|
artikel
|
| 47 |
Resonance calculation based on the deep learning method for treating the non-uniform fuel temperature distribution in PWRs
|
Cao, Lu
|
|
|
160 |
C |
p.
|
artikel
|
| 48 |
Retraction notice to “Reactivity worth measurement of the lead target on VENUS-II light water reactor and validation of evaluated nuclear data” [ANE 154 (2021) 108106]
|
Jiang, Wei
|
|
|
160 |
C |
p.
|
artikel
|
| 49 |
Signatures of plutonium diversion in Molten Salt Reactor dynamics
|
Wheeler, Alexander M.
|
|
|
160 |
C |
p.
|
artikel
|
| 50 |
Spent nuclear fuel interim dry storage; Design requirements, most common methods, and evolution: A review
|
El-Samrah, Moamen G.
|
|
|
160 |
C |
p.
|
artikel
|
| 51 |
Study on the pulse parameters of fast periodic pulsed reactor under stable operation
|
Zhang, Liang
|
|
|
160 |
C |
p.
|
artikel
|
| 52 |
Supercritical CO2 flow instability in natural circulation loop: CFD analysis
|
Wahidi, Tabish
|
|
|
160 |
C |
p.
|
artikel
|
| 53 |
Theoretical investigation on the solution of the single-phase flow instability among parallel U-tubes
|
Hao, J.L.
|
|
|
160 |
C |
p.
|
artikel
|
| 54 |
Three-dimensional reconstruction and measurement of fuel assemblies for sodium-cooled fast reactor using linear structured light
|
Zhao, Jianping
|
|
|
160 |
C |
p.
|
artikel
|
| 55 |
Time sequence method for prompt neutron decay constant determination
|
Wen, Jie
|
|
|
160 |
C |
p.
|
artikel
|
| 56 |
Transient testing of uranium silicide fuel in zircaloy and silicon carbide cladding
|
Kamerman, David
|
|
|
160 |
C |
p.
|
artikel
|
| 57 |
Unavailability analysis of a digital hybrid platform for reactor protection systems
|
Jeong, Jiye
|
|
|
160 |
C |
p.
|
artikel
|
| 58 |
Uncertainty analysis of reactivity feedback coefficient for LFR core power control system during reactivity insertion accident
|
Liu, Yinuo
|
|
|
160 |
C |
p.
|
artikel
|
| 59 |
Uncertainty quantification and software risk analysis for digital twins in the nearly autonomous management and control systems: A review
|
Lin, Linyu
|
|
|
160 |
C |
p.
|
artikel
|
| 60 |
Ventilation pattern and heat dissipation characteristics of a vertical dry storage cask for spent nuclear fuel: Wind tunnel experiments and CFD simulations
|
Wang, Yao-Hung
|
|
|
160 |
C |
p.
|
artikel
|
| 61 |
Visualization experimental study on axial flow-induced vibration of slender cantilever rod for reactor
|
Li, Xin
|
|
|
160 |
C |
p.
|
artikel
|
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