| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A Bayesian Inference driven computational framework for seismic risk assessment using large-scale nonlinear finite element analyses
|
Tadinada, Sashi Kanth
|
|
|
130 |
C |
p.
|
artikel
|
| 2 |
A comparison of spent resin degradation by Fenton and O3-Fenton process
|
Feng, Wendong
|
|
|
130 |
C |
p.
|
artikel
|
| 3 |
An estimation of weapon-grade plutonium production from 5 MWe YongByon reactor through MCNP6 core depletion analysis
|
Park, Geon Hee
|
|
|
130 |
C |
p.
|
artikel
|
| 4 |
Application of polyaniline nanocomposites in the trapping of thorium ions from aqueous solutions:Adsorption equilibrium, kinetics and thermodynamics
|
Abdi, Sara
|
|
|
130 |
C |
p.
|
artikel
|
| 5 |
A RELAP5-3D/LSTM model for the analysis of drywell cooling fan failure
|
Guillen, D.P.
|
|
|
130 |
C |
p.
|
artikel
|
| 6 |
A study on object recognition using deep learning for optimizing categorization of radioactive waste
|
Kim, Jeong-Guk
|
|
|
130 |
C |
p.
|
artikel
|
| 7 |
Comparison of Reduced-Basis techniques for the model order reduction of parametric incompressible fluid flows
|
German, Péter
|
|
|
130 |
C |
p.
|
artikel
|
| 8 |
Computational burnup analysis of the TRIGA Mark II research reactor fuel
|
Pungerčič, Anže
|
|
|
130 |
C |
p.
|
artikel
|
| 9 |
Design and application of supervisory control based on neural network PID controllers for pressurizer system
|
Hosseini, Seyed Ali
|
|
|
130 |
C |
p.
|
artikel
|
| 10 |
3D neutronic/thermal-hydraulic nuclear reactor core calculation (NRCC) code development for PWRs
|
Aghili Nasr, Mahdi
|
|
|
130 |
C |
p.
|
artikel
|
| 11 |
Editorial Board
|
|
|
|
130 |
C |
p.
|
artikel
|
| 12 |
Evaluation of crack growth of chloride-induced stress corrosion cracking in dry storage system under different environmental conditions
|
Wang, Wen-Yu
|
|
|
130 |
C |
p.
|
artikel
|
| 13 |
Experimental analysis of fiber optic responses in ionizing radiation environments for distributed sensing applications
|
Stratton, Charles
|
|
|
130 |
C |
p.
|
artikel
|
| 14 |
Experimental and Monte Carlo simulation study on potential new composite materials to moderate neutron-gamma radiation
|
Aygün, Bünyamin
|
|
|
130 |
C |
p.
|
artikel
|
| 15 |
Fenton oxidative degradation of spent organic solvents from nuclear fuel reprocessing plant
|
Wang, Chao
|
|
|
130 |
C |
p.
|
artikel
|
| 16 |
Hydraulic forces acting on full cross section fuel assemblies with 17×17 fuel rods
|
Bieder, Ulrich
|
|
|
130 |
C |
p.
|
artikel
|
| 17 |
Improvement and validation of RELAP5/SCDAP code on evaluating the graphite behavior during oxidation process
|
Chai, Penghui
|
|
|
130 |
C |
p.
|
artikel
|
| 18 |
Innovative designed fuel pin of conceptual semi-heavy water research reactor with improved reactor safety
|
Rahimi, Ghasem
|
|
|
130 |
C |
p.
|
artikel
|
| 19 |
Methodology for inferring reactor core power distribution from an optical fiber based gamma thermometer array
|
Birri, Anthony
|
|
|
130 |
C |
p.
|
artikel
|
| 20 |
Methodology for ultrasonic inspection of dispersion type U–Mo fuel plates
|
Alarcón, María J.
|
|
|
130 |
C |
p.
|
artikel
|
| 21 |
Modeling and simulation of onset of condensation-induced water hammer
|
Hibiki, Takashi
|
|
|
130 |
C |
p.
|
artikel
|
| 22 |
Neutronic analyses of americium burning U-free inert matrix fuels
|
Shelley, Afroza
|
|
|
130 |
C |
p.
|
artikel
|
| 23 |
Non-linear dynamics of single phase rectangular natural circulation loop
|
Goyal, Vishal
|
|
|
130 |
C |
p.
|
artikel
|
| 24 |
Novel scintillation properties by entrapping ZnO: Ga nanocrystals in epoxy polymer
|
Alamdari, S.
|
|
|
130 |
C |
p.
|
artikel
|
| 25 |
Nuclear data uncertainty propagation to the main physical parameters of NUR research reactor
|
Sellaoui, N.
|
|
|
130 |
C |
p.
|
artikel
|
| 26 |
Preparation and properties characterization of a novel soft robots partially made of silicone/W-based composites for gamma ray shielding
|
Wang, Jie
|
|
|
130 |
C |
p.
|
artikel
|
| 27 |
Regress in nuclear district heating. The need for rethinking cogeneration
|
Lipka, Maciej
|
|
|
130 |
C |
p.
|
artikel
|
| 28 |
Review: Steam cavity characteristics of steam submerged jet condensation at SC regime
|
Zhao, Quanbin
|
|
|
130 |
C |
p.
|
artikel
|
| 29 |
Scale effect of amount of molten corium and outlet diameters on corium spreading
|
Yokoyama, Ryo
|
|
|
130 |
C |
p.
|
artikel
|
| 30 |
Shielding performance of heavy-weight ultra-high-performance concrete against nuclear radiation
|
Khan, Muhammad Umar
|
|
|
130 |
C |
p.
|
artikel
|
| 31 |
The effect of operational conditions on the stability and efficiency of an emulsion liquid membrane system for removal of uranium
|
Arabi Ardehali, Babak
|
|
|
130 |
C |
p.
|
artikel
|
| 32 |
Thermal-hydraulic and solid mechanics safety analysis for VVER-1000 reactor using analytical and CFD approaches
|
Mohsen, Mohamed Y.M.
|
|
|
130 |
C |
p.
|
artikel
|
| 33 |
Verification of the current coupling collision probability method with orthogonal flux expansion for the assembly calculations
|
Litskevich, Dzianis
|
|
|
130 |
C |
p.
|
artikel
|
Tijdschrift beschrijving