| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A detailed design for a radioactive waste safety management system using ICT technologies
|
Park, Hee-Seoung
|
|
|
149 |
C |
p.
|
artikel
|
| 2 |
Analysis on waterproofing design in CCS pump building of PWR under main feed water pipe broken accident
|
Zhao, Haiqi
|
|
|
149 |
C |
p.
|
artikel
|
| 3 |
An axisymmetric multiphase moving particle semi-implicit method for simulation of 3D axisymmetric flow
|
Gao, Jinchen
|
|
|
149 |
C |
p.
|
artikel
|
| 4 |
Applications of neutron computed tomography to thermal-hydraulics research
|
Lohvithee, Manasavee
|
|
|
149 |
C |
p.
|
artikel
|
| 5 |
Applications of Soft Computing in nuclear power plants: A review
|
Ramezani, Iman
|
|
|
149 |
C |
p.
|
artikel
|
| 6 |
Assessment of advanced boiling flow and heat transfer models for PHWR conditions
|
Podila, Krishna
|
|
|
149 |
C |
p.
|
artikel
|
| 7 |
A universal formula for high-order added mass of reactor core barrel with lower core plate immersed in fluid
|
Zhang, Yu
|
|
|
149 |
C |
p.
|
artikel
|
| 8 |
Borotellurite glass system doped with ZrO2, potential use for radiation shielding
|
Abdelghany, Y.A.
|
|
|
149 |
C |
p.
|
artikel
|
| 9 |
Conditions leading to and the characteristics of exothermic processes in condensed mixtures used in technological processes of hydrometallurgical reprocessing of spent nuclear fuel
|
Nazin, Evgeniy
|
|
|
149 |
C |
p.
|
artikel
|
| 10 |
Design of multi-module adaptive fuzzy power tracking control for nonlinear four-point reactor core model under multiple transient conditions
|
Aftab, Adnan
|
|
|
149 |
C |
p.
|
artikel
|
| 11 |
Destruction of the Tokem-308 cation-exchange resin (analog of KU-2-8) by its gas-phase treatment in a nitrating atmosphere
|
Kulyukhin, Sergey A.
|
|
|
149 |
C |
p.
|
artikel
|
| 12 |
Do renewable and nuclear energy enhance environmental quality in France? A new EKC approach with the load capacity factor
|
Pata, Ugur Korkut
|
|
|
149 |
C |
p.
|
artikel
|
| 13 |
Editorial Board
|
|
|
|
149 |
C |
p.
|
artikel
|
| 14 |
Evaluation of optimized machine learning models for nuclear reactor accident prediction
|
Racheal, Suubi
|
|
|
149 |
C |
p.
|
artikel
|
| 15 |
Experimental study of steam-air mixture thermal stratification during the dropping of containment pressure
|
Chen, Weixiong
|
|
|
149 |
C |
p.
|
artikel
|
| 16 |
Finite element based fuel performance investigation of U3Si2–FeCrAl design under normal and RIA conditions
|
Deng, Chaoqun
|
|
|
149 |
C |
p.
|
artikel
|
| 17 |
Gels, coatings and foams for radioactive surface decontamination: State of the art and challenges for the nuclear industry
|
Gossard, Alban
|
|
|
149 |
C |
p.
|
artikel
|
| 18 |
Monte Carlo simulation of the mass attenuation coefficient and effective atomic number of the Eremurus-Rhizophora ssp. particleboard phantom at the mammography energy range
|
Tousi, Ehsan Taghizadeh
|
|
|
149 |
C |
p.
|
artikel
|
| 19 |
Numerical and experimental study on natural convection outside tube bundle under small convection temperature difference
|
Xu, Junxiu
|
|
|
149 |
C |
p.
|
artikel
|
| 20 |
Pre-conceptual high temperature gas cooled microreactor design utilizing two-phase composite moderators. Part II: Design space and safety characteristics
|
Duchnowski, Edward M.
|
|
|
149 |
C |
p.
|
artikel
|
| 21 |
Pre-conceptual high temperature gas-cooled microreactor design utilizing two-phase composite moderators. Part I: Microreactor design and reactor performance
|
Duchnowski, Edward M.
|
|
|
149 |
C |
p.
|
artikel
|
| 22 |
Preliminary conceptual design of fast neutron spectrum nuclear thermal rocket cores using monolithic uranium nitride fuel
|
Youinou, G.J.
|
|
|
149 |
C |
p.
|
artikel
|
| 23 |
Quantifying performance of passive systems in an integrated small modular reactor under uncertainties using multilevel flow modelling and stochastic collocation method
|
Huang, Zhi'ao
|
|
|
149 |
C |
p.
|
artikel
|
| 24 |
Radiophobia: Useful concept, or ostracising term?
|
Lindberg, John C.H.
|
|
|
149 |
C |
p.
|
artikel
|
| 25 |
Research on compliance between large break LOCA of HPR1000 and new LOCA acceptance criterion 10CFR50.46c
|
Weiwei, Wang
|
|
|
149 |
C |
p.
|
artikel
|
| 26 |
Research on equipment survivability assessment in severe accidents for CANDU6
|
Huang, Gaofeng
|
|
|
149 |
C |
p.
|
artikel
|
| 27 |
Simulation of the processes occurring during steam generator tube rupture in the lead cooled reactor unit using HYDRA-IBRAE/LM code
|
Alipchenkov, V.M.
|
|
|
149 |
C |
p.
|
artikel
|
| 28 |
Sites selection for a potential radioactive waste repository in Peninsular Malaysia: GIS-based weight linear combination and multi-criteria decision-making analysis
|
Lim, You Jinq
|
|
|
149 |
C |
p.
|
artikel
|
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