| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A control-oriented hybrid modeling method for small pressurized water reactors based on linear models and neural networks
|
Zhu, Ze
|
|
|
222 |
C |
p.
|
artikel
|
| 2 |
Advanced CFD analysis of impurity formation and transport in liquid Lead-Bismuth Eutectic (LBE) loop systems
|
Lu, Dingsheng
|
|
|
222 |
C |
p.
|
artikel
|
| 3 |
A hybrid few-group homogenization approach for coupled nodal diffusion-thermal hydraulic analysis of nuclear thermal propulsion reactors
|
Smith, Jacob D.
|
|
|
222 |
C |
p.
|
artikel
|
| 4 |
A mathematical approach to using the forgetting curve to evaluate experience and training factors in human reliability analysis
|
Kim, Jisuk
|
|
|
222 |
C |
p.
|
artikel
|
| 5 |
Analysing hydrogen behaviour in liner claddings using OFFBEAT fuel performance code
|
Verma, L.
|
|
|
222 |
C |
p.
|
artikel
|
| 6 |
Analysis of space nuclear reactor under accident conditions with CFD simulation and interpretable machine learning algorithm
|
Song, Meiqi
|
|
|
222 |
C |
p.
|
artikel
|
| 7 |
An approach for spent nuclear fuel containment integrity verification using gas tagging
|
Imholte, D.D.
|
|
|
222 |
C |
p.
|
artikel
|
| 8 |
An enhanced Signed Directed Graph method for system reliability analysis
|
Wang, Dagui
|
|
|
222 |
C |
p.
|
artikel
|
| 9 |
A new format for the elastic scattering differential cross section covariance of charged particles
|
Han, Xu
|
|
|
222 |
C |
p.
|
artikel
|
| 10 |
An interpretable deep transfer learning method for fault diagnosis of nuclear power plants under multiple power level conditions
|
Ma, Zhanguo
|
|
|
222 |
C |
p.
|
artikel
|
| 11 |
An investigation of flow-induced vibrations (FIV) during cold testing on a helical tube steam generator for a high-temperature gas-cooled reactor (HTGR)
|
Subhan, Muhammad
|
|
|
222 |
C |
p.
|
artikel
|
| 12 |
Autonomous orphan source search using probabilistic methods
|
Chepkwony, Amos Kipkosgei
|
|
|
222 |
C |
p.
|
artikel
|
| 13 |
CFD study on lift force correlations of a single motion bubble in shear flow
|
Xu, Shuying
|
|
|
222 |
C |
p.
|
artikel
|
| 14 |
Computational homogenization of thermomechanical properties for Fully Ceramic Microencapsulated fuel with 3D printed SiC matrix
|
Chen, Yiwen
|
|
|
222 |
C |
p.
|
artikel
|
| 15 |
Conceptual core design study of a maritime molten salt fast reactor
|
Go, Yubin
|
|
|
222 |
C |
p.
|
artikel
|
| 16 |
Deconvolution approach for determining absolute prompt γ -ray intensities of 52V yielded from the 51V(n, γ )52V reaction at the Dalat Nuclear Research Reactor
|
Chau, Thanh Tai
|
|
|
222 |
C |
p.
|
artikel
|
| 17 |
Delayed neutrons yields and group abundances for thermal-neutron-induced fission of 233U
|
Geslot, B.
|
|
|
222 |
C |
p.
|
artikel
|
| 18 |
Direct NeTS sampling of nuclear graphite S ( α , β , T ) in Serpent
|
Crozier, Jonathan P.W.
|
|
|
222 |
C |
p.
|
artikel
|
| 19 |
Ecofriendly technique for the treatment of water contaminated with stable and radioactive cobalt through an adsorption process using dried prickly pear residues
|
Saleh, Hosam M.
|
|
|
222 |
C |
p.
|
artikel
|
| 20 |
Editorial Board
|
|
|
|
222 |
C |
p.
|
artikel
|
| 21 |
Effect of buoyancy-induced natural convection heat transfer on thermal qualification of lead-shielded radioactive material transport packages
|
Kota, Sampath Bharadwaj
|
|
|
222 |
C |
p.
|
artikel
|
| 22 |
Error detection in underwater laser cutting for nuclear facility dismantlement using hydrophone and AI techniques
|
Kim, Ikjune
|
|
|
222 |
C |
p.
|
artikel
|
| 23 |
Evaluation of shielding effectiveness of coated alloy 709 for nuclear spent fuel dry cask canisters
|
Alsmadi, Zeinab Y.
|
|
|
222 |
C |
p.
|
artikel
|
| 24 |
Experimental research on the startup and shutdown heat transfer behavior of the coupling system of multi-stage heat pipes and radiators
|
Liu, Limin
|
|
|
222 |
C |
p.
|
artikel
|
| 25 |
Fault detection for nuclear power plant based on improved moving window and sparse autoencoder
|
Zhu, Shaomin
|
|
|
222 |
C |
p.
|
artikel
|
| 26 |
Impact of different TRU compositions on system response during an unprotected station blackout in small lead-cooled reactors
|
Dehlin, Fredrik
|
|
|
222 |
C |
p.
|
artikel
|
| 27 |
Impact of energy collapsing on the effective neutron lifetime
|
Dulla, S.
|
|
|
222 |
C |
p.
|
artikel
|
| 28 |
Increasing the operational safety margin of the Indian Pressurized Heavy Water Reactor (IPHWR-220) by introducing accident-tolerant fuel instead of natural uranium
|
Mohsen, Mohamed Y.M.
|
|
|
222 |
C |
p.
|
artikel
|
| 29 |
Investigation of thermo-mechanical behaviour of 220MWe IPHWR channel under accdiental scenario (LOCA)
|
Raj, Shivam
|
|
|
222 |
C |
p.
|
artikel
|
| 30 |
Linear active disturbance rejection control of CEFR power and control performance verification with hardware-in-the-loop simulation
|
Fan, Ziqi
|
|
|
222 |
C |
p.
|
artikel
|
| 31 |
Mechanical equipment failure rate prediction method for nuclear power plants
|
Wu, Yi
|
|
|
222 |
C |
p.
|
artikel
|
| 32 |
Mechanistic CHF model development based on the liquid sublayer dryout model for flow boiling phenomena under IVR-ERVC conditions
|
Lee, Min Suk
|
|
|
222 |
C |
p.
|
artikel
|
| 33 |
New approach to evaluate axial deformation of PWR fuel assembly on criticality safety of transport packages under impact accidents
|
Dai, Xinling
|
|
|
222 |
C |
p.
|
artikel
|
| 34 |
Numerical study of boiling crisis characteristics in helical cruciform fuel with axially non-uniform power distribution
|
Huang, Zijian
|
|
|
222 |
C |
p.
|
artikel
|
| 35 |
Numerical study of effects of system variables on rising vapour bubble in convective boiling conditions
|
Sharif, Syed Ahsan
|
|
|
222 |
C |
p.
|
artikel
|
| 36 |
Numerical study of helium bubble behavior and its effect on heat transfer of liquid lithium on an inclined wall
|
Zhang, Wenchao
|
|
|
222 |
C |
p.
|
artikel
|
| 37 |
Optimizing sorosilicate crystals for γ-ray shielding: Role of density and SiO2 content
|
Khattari, Z.Y.
|
|
|
222 |
C |
p.
|
artikel
|
| 38 |
Performance improvement of mechanical, chemical and radiation protection of Ag+-doped bismuth silicate glasses for radiation shielding applications
|
Ebrahium, Mohamad M.
|
|
|
222 |
C |
p.
|
artikel
|
| 39 |
Performance of the borate glasses doped with some rare earth compounds during the neutron irradiation: Analysis for the mass removal cross section of fast neutrons and secondary gamma-ray emission
|
Tashlykov, O.L.
|
|
|
222 |
C |
p.
|
artikel
|
| 40 |
Physics-enhanced machine learning for probabilistic risk assessment in nuclear safety: An overview, recent developments, and perspectives
|
Lye, Adolphus
|
|
|
222 |
C |
p.
|
artikel
|
| 41 |
Reactor power regulation of a small pressurized water reactor based on linear active disturbance rejection control with gain scheduling
|
Fan, Ziqi
|
|
|
222 |
C |
p.
|
artikel
|
| 42 |
Research of the flow boiling heat transfer on surfaces of stainless steel and anodized-chromium in mini-channel
|
Zhang, Luteng
|
|
|
222 |
C |
p.
|
artikel
|
| 43 |
Study on non-uniform control rod with BeO reflectors
|
Liu, Feilong
|
|
|
222 |
C |
p.
|
artikel
|
| 44 |
Study on the characteristics of vibration acoustic signals and rupture grading for reactor pipeline leaks
|
Zhao, Xinyu
|
|
|
222 |
C |
p.
|
artikel
|
| 45 |
Tightly coupled multi-physics algorithm for control rod follow mode based on Newton-Krylov method
|
Peng, Xinru
|
|
|
222 |
C |
p.
|
artikel
|
| 46 |
Uncertainty quantification of Cl-35 nuclear data on a Molten Chloride Fast Reactor
|
Valentin, Jean-Baptiste
|
|
|
222 |
C |
p.
|
artikel
|
| 47 |
Verification of practical modeling approaches of an MSLB event simulation: A CFD contribution
|
Fogliatto, Ezequiel
|
|
|
222 |
C |
p.
|
artikel
|
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