| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A detailed review on critical flow experiments and models
|
Tian, Gengyuan
|
|
|
219 |
C |
p.
|
artikel
|
| 2 |
A method fusing self-attention-SPN and NSGA-III for multi-objective radiation shielding design optimization
|
He, Li
|
|
|
219 |
C |
p.
|
artikel
|
| 3 |
A new mathematical model for the radionuclide concentrations in crops for the generic biosphere assessment
|
Kim, Dongki
|
|
|
219 |
C |
p.
|
artikel
|
| 4 |
A novel methodology assessment to study the performance of the physical protection system for enhancing the security of nuclear and other radioactive materials during transport
|
Touarsi, Amal
|
|
|
219 |
C |
p.
|
artikel
|
| 5 |
A review on nuclear emergency preparedness and response management
|
Fan, Yipeng
|
|
|
219 |
C |
p.
|
artikel
|
| 6 |
A semi-analytical method for modelling station blackout transients in liquid metal-cooled reactors
|
Wallenius, Janne
|
|
|
219 |
C |
p.
|
artikel
|
| 7 |
A semi-implicit Chord Length Sampling method for dispersion fuel analysis
|
Tan, Zhe Chuan
|
|
|
219 |
C |
p.
|
artikel
|
| 8 |
ASTEC core degradation calculations in support of Level-2 Probabilistic Safety Assessment for 1300MWe French reactors: Methodology and preliminary results
|
Monestier, M.
|
|
|
219 |
C |
p.
|
artikel
|
| 9 |
Characteristics analysis of the typical vehicle-mounted megawatt-scale heat pipe cooled reactor power system
|
Lin, Henglong
|
|
|
219 |
C |
p.
|
artikel
|
| 10 |
Cluster-dynamics study on the evolution of dislocation loops in molybdenum: The role of defect diffusion coefficient and equilibrium concentration
|
Xie, Teng
|
|
|
219 |
C |
p.
|
artikel
|
| 11 |
Comparison of high-fidelity transport code predictions against the NECTAR intra-pin reaction rate measurements
|
Mager, Tom
|
|
|
219 |
C |
p.
|
artikel
|
| 12 |
Corrigendum to “Neutronic analysis for withdrawal of TRIGA MARK II reactor control rods using OpenMC program” [Ann. Nucl. Energy 217 (2025) 111330]
|
Prasetya, Fajri
|
|
|
219 |
C |
p.
|
artikel
|
| 13 |
Deep learning applications on satellite imagery datasets for nuclear nonproliferation and counter-proliferation
|
Han, Jae-Jun
|
|
|
219 |
C |
p.
|
artikel
|
| 14 |
Development and application of a neutronics/thermal-hydraulics coupling code based on system code and Anderson acceleration
|
Yang, Bowen
|
|
|
219 |
C |
p.
|
artikel
|
| 15 |
Development and application of three-dimensional multi-physics and multi-scale coupling program for lead cooled fast reactor
|
Dong, Sifan
|
|
|
219 |
C |
p.
|
artikel
|
| 16 |
Development of a thermal–hydraulic system code with multi-dimensional modeling for liquid metal pool-type fast reactor and preliminary verification and validation
|
Hou, Jieming
|
|
|
219 |
C |
p.
|
artikel
|
| 17 |
Dynamics modeling of molten salt reactor with reduced and expanded representations of delayed neutron precursors
|
Abuqudaira, Thabit
|
|
|
219 |
C |
p.
|
artikel
|
| 18 |
Editorial Board
|
|
|
|
219 |
C |
p.
|
artikel
|
| 19 |
Experimental investigation of saturated flow boiling of water in vertical helically coiled tubes
|
Su, Yuqing
|
|
|
219 |
C |
p.
|
artikel
|
| 20 |
Experimental research on fluid elastic instability in tube bundles subjected to single-phase water cross-flow
|
Yin, Yibo
|
|
|
219 |
C |
p.
|
artikel
|
| 21 |
Experimental study of internal flow induced vibration of tray rod assembly during on-power handling in a typical Indian research reactor
|
Ravi Kiran, A.
|
|
|
219 |
C |
p.
|
artikel
|
| 22 |
Experimental study on light gas transport during containment venting by using the large-scale test facility CIGMA
|
Soma, Shu
|
|
|
219 |
C |
p.
|
artikel
|
| 23 |
Impact of U-10Mo HALEU Fuel Element Tolerances on the Massachusetts Institute of Technology Reactor safety and operational performance – Neutronics
|
Mascolino, Valerio
|
|
|
219 |
C |
p.
|
artikel
|
| 24 |
Impact of U-10Mo HALEU fuel element tolerances on the Massachusetts Institute of Technology reactor safety and operational performance – Thermal hydraulics
|
Yang, Sero
|
|
|
219 |
C |
p.
|
artikel
|
| 25 |
Improved CFD modeling of radial void fraction distribution in flow boiling: A novel approach for wide-ranging operating conditions
|
Peng, Yujiao
|
|
|
219 |
C |
p.
|
artikel
|
| 26 |
Improvement of in-vessel corium transient stratification modelling regarding the uranium and zirconium phase partitioning
|
Mativet, J.
|
|
|
219 |
C |
p.
|
artikel
|
| 27 |
Improves the stability of containment leakage rate in constant pressure method by linear fitting analysis model
|
Jianfa, Li
|
|
|
219 |
C |
p.
|
artikel
|
| 28 |
Investigating thermal and mechanical behavior for two thorium fuel types in a PWR
|
Refaey, Ahmed M.
|
|
|
219 |
C |
p.
|
artikel
|
| 29 |
Investigation of added mass coefficient of helical tube bundles in steam generator based on finite element modal analysis
|
Chen, Xiaodong
|
|
|
219 |
C |
p.
|
artikel
|
| 30 |
Investigation of coarse mesh acceleration methods for the SN nodal method in unstructured geometries
|
Xu, Haoxiang
|
|
|
219 |
C |
p.
|
artikel
|
| 31 |
Modeling and simulating of the gas flow inside a molecular pump with different geometries by Monte Carlo method to predict the compression ratio
|
Khajenoori, Masoud
|
|
|
219 |
C |
p.
|
artikel
|
| 32 |
Modeling, verification and validation of multiple PWR depletion cycles with DRAGON and PARCS
|
Meunier, B.
|
|
|
219 |
C |
p.
|
artikel
|
| 33 |
Neutron resonance integral analysis of 238U within resolved resonance region
|
Pan, Yufei
|
|
|
219 |
C |
p.
|
artikel
|
| 34 |
Numerical investigation on deposition characteristics of ferroferric oxide particles fouling in 2 × 2 petal-shaped fuel rod
|
Zhao, Yu
|
|
|
219 |
C |
p.
|
artikel
|
| 35 |
Optimization of heterogeneous parallel algorithm for Monte Carlo neutron transport simulation aiming at thread divergence Issues
|
Zhang, Xian
|
|
|
219 |
C |
p.
|
artikel
|
| 36 |
Parameter identification of fluid field based on CFD reduced-order model and 3D-Var data assimilation
|
Dai, Chuqiao
|
|
|
219 |
C |
p.
|
artikel
|
| 37 |
Parametric study of the computational model on fuel and fission products characteristics analysis of HTR-PM equilibrium core
|
Raza, Sohail Ahmad
|
|
|
219 |
C |
p.
|
artikel
|
| 38 |
PINN and KAN temperature prediction of carbon Fiber/Epoxy composite materials irradiated by nuclear environment simulated intense heat fluxes
|
Han, Xiaoxiang
|
|
|
219 |
C |
p.
|
artikel
|
| 39 |
Preparation of UCO sols suitable for gelation into microspheres by sol–gel process with glucose
|
Zhang, Wenjing
|
|
|
219 |
C |
p.
|
artikel
|
| 40 |
Radioisotope production at the advanced test reactor: process and lessons learned
|
Zillmer, Andrew
|
|
|
219 |
C |
p.
|
artikel
|
| 41 |
Reactivity measurement using pulsed neutron source methods on VR-1 and VR-2 reactors and their verification by SERPENT code
|
Herčík, Michal
|
|
|
219 |
C |
p.
|
artikel
|
| 42 |
Research on sensor anomaly detection and fault location in nuclear power plants based on GAN-IAAKR model
|
Gao, Jiarong
|
|
|
219 |
C |
p.
|
artikel
|
| 43 |
Scale model for investigating two-phase flow instability in a PWR passive residual heat removal system
|
Jo, Jong Chull
|
|
|
219 |
C |
p.
|
artikel
|
| 44 |
Sensitivity and uncertainty analysis in pebble-bed reactors: A study using the High-Temperature Code Package (HCP)
|
Yaseen, Mahmoud
|
|
|
219 |
C |
p.
|
artikel
|
| 45 |
Simulation of pulsatile flow and heat transfer characteristics of liquid-sodium in annular tight-lattice hexagonal rod bundles
|
Ala, Ayodeji A.
|
|
|
219 |
C |
p.
|
artikel
|
| 46 |
Sodium dynamic behavior simulation and analysis under whole large leakage sodium-water reaction accident process
|
Bai, Xi
|
|
|
219 |
C |
p.
|
artikel
|
| 47 |
Synthesis and radiation attenuation properties of polymethyl methacrylate/apatite-wollastonite composites for advanced shielding applications
|
Alsaiari, Norah Salem
|
|
|
219 |
C |
p.
|
artikel
|
| 48 |
Systematic generation of effective thermophysical and thermo-mechanical properties for reduced-order modeling of TRISO fuel pellets
|
Heflin, Samuel
|
|
|
219 |
C |
p.
|
artikel
|
| 49 |
The CoRREx neutron spectrum filtering campaign at VENUS-F for calculation-to-experiment discrepancy interpretation
|
Grimaldi, Federico
|
|
|
219 |
C |
p.
|
artikel
|
| 50 |
The design and calibration of a new differential calorimetric dedicated to nuclear heating measurements
|
Zhang, Junxin
|
|
|
219 |
C |
p.
|
artikel
|
| 51 |
Three-dimensional refined burnup characteristics analysis of Helical Cruciform Fuel
|
Duan, Qianni
|
|
|
219 |
C |
p.
|
artikel
|
| 52 |
Transport-corrected flux-moment homogenization method for generating P0 multigroup cross-section based on continuous energy Monte-Carlo
|
Shen, Yuyang
|
|
|
219 |
C |
p.
|
artikel
|
Tijdschrift beschrijving