| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A comparative analysis of detailed and reduced CFD approaches to model wire-wrapped fuel bundles for LMFBRs applications
|
Halim, O.
|
|
|
211 |
C |
p.
|
artikel
|
| 2 |
A comparative study of machine learning approaches for identification of perturbed fuel assemblies in WWER-type nuclear reactors
|
Kamkar, A.
|
|
|
211 |
C |
p.
|
artikel
|
| 3 |
A composite fault diagnosis method for nuclear power plant rotor system based on symmetrized dot pattern and residual neural network
|
Yin, Wenzhe
|
|
|
211 |
C |
p.
|
artikel
|
| 4 |
A comprehensive overview of advancements, applications, and impact of supercritical fluid natural circulation loops
|
Kumar Rai, Santosh
|
|
|
211 |
C |
p.
|
artikel
|
| 5 |
A computational framework to support probabilistic criticality modelling for the geological disposal of radioactive waste
|
Adam Paxton, E.
|
|
|
211 |
C |
p.
|
artikel
|
| 6 |
Adjusting aluminum elastic scattering data from the TALYS nuclear reaction code based upon fast criticalities
|
Pelloni, Sandro
|
|
|
211 |
C |
p.
|
artikel
|
| 7 |
Advancing source reactor-type discrimination using machine learning techniques and SFCOMPO-2.0 experimental database
|
Wang, Tianxiang
|
|
|
211 |
C |
p.
|
artikel
|
| 8 |
Alternative core configurations analysis to improve the neutronics performance of modular gas cooled fast reactor
|
Islam, Shohanul
|
|
|
211 |
C |
p.
|
artikel
|
| 9 |
A multi-scale coupling algorithm for burnup calculation of dispersed particulate poison
|
Li, Junxian
|
|
|
211 |
C |
p.
|
artikel
|
| 10 |
Analysis of internal flow excitation characteristics of reactor coolant pump based on DMD
|
Yun, Long
|
|
|
211 |
C |
p.
|
artikel
|
| 11 |
Analysis of swarm flow and bubble residence time under pool scrubbing conditions
|
Kong, Fanli
|
|
|
211 |
C |
p.
|
artikel
|
| 12 |
Analysis of the influence of bottom flow holes in control rod guide tubes on flow field and control rod displacement
|
Qiu, Hanrui
|
|
|
211 |
C |
p.
|
artikel
|
| 13 |
A neutronic comparative study of reflectors in radially and axially heterogeneous cores for the ABR-1000 sodium cooled fast reactor
|
Niloy, Md. Hasebul Hasan
|
|
|
211 |
C |
p.
|
artikel
|
| 14 |
A novel hybrid model for annular linear induction pump
|
Zhu, Sixian
|
|
|
211 |
C |
p.
|
artikel
|
| 15 |
Applicability domain and gaps of SNF decay heat validation data – A similarity-based approach
|
Shama, Ahmed
|
|
|
211 |
C |
p.
|
artikel
|
| 16 |
Application of the PSI cycle check-up methodology for full-core Monte Carlo simulations verified using pin power estimates and validated for hot zero power conditions
|
Berry, Louis
|
|
|
211 |
C |
p.
|
artikel
|
| 17 |
A realistic TRACE PWR LOCA model with application to high-burnup analysis
|
Wysocki, Aaron
|
|
|
211 |
C |
p.
|
artikel
|
| 18 |
Assessing organizational vulnerability of nuclear power plants using AHP-fuzzy sets method
|
Wang, Ye
|
|
|
211 |
C |
p.
|
artikel
|
| 19 |
Assessment and improvement of numerical model for steam condensation with non-condensable gases on all-curvature surfaces in NPP containments
|
Li, Gonglin
|
|
|
211 |
C |
p.
|
artikel
|
| 20 |
A study on in-situ characterization technology development for clearance verification of radioactive waste from nuclear decommissioning
|
Kim, Kyungmin
|
|
|
211 |
C |
p.
|
artikel
|
| 21 |
A study on the optimization through the evaluation of radiation exposure by scenarios during steam generator dismantling
|
Shin, Jonghyun
|
|
|
211 |
C |
p.
|
artikel
|
| 22 |
Autonomous anomaly detection of proliferation in the AGN-201 nuclear reactor digital twin
|
Treviño, Eduardo
|
|
|
211 |
C |
p.
|
artikel
|
| 23 |
Broomstick experiment with copper in VR-1 reactor
|
Košťál, Michal
|
|
|
211 |
C |
p.
|
artikel
|
| 24 |
Californium-252 production at the High Flux Isotope Reactor - II: Comparison between the highly enriched uranium and a proposed low-enriched uranium core
|
Chandler, David
|
|
|
211 |
C |
p.
|
artikel
|
| 25 |
Californium-252 production at the High Flux Isotope Reactor − I: Validation study using campaign data
|
Hartanto, Donny
|
|
|
211 |
C |
p.
|
artikel
|
| 26 |
Contribution of transient heat transfer to overpressure protection in a passive Boiling Water Reactor
|
Pomogaev, Aleksandr
|
|
|
211 |
C |
p.
|
artikel
|
| 27 |
Corrosion of structural materials in NaF-NaBF4 molten salt
|
Cihlář, Michal
|
|
|
211 |
C |
p.
|
artikel
|
| 28 |
CORTEX experiments – Part I: Modulation campaigns in AKR-2 & CROCUS for the validation of neutron noise codes
|
Lamirand, Vincent
|
|
|
211 |
C |
p.
|
artikel
|
| 29 |
Coupled analysis of oxidation corrosion and heat transfer in lead-cooled fast reactors
|
Zhang, Yan
|
|
|
211 |
C |
p.
|
artikel
|
| 30 |
Coupling of MELCOR with surrogate model for quench estimation of conical debris beds
|
Wang, Wanhong
|
|
|
211 |
C |
p.
|
artikel
|
| 31 |
Critical response to M. Worrall et al. Published in Annals of Nuclear Energy 207 (2024) 110731
|
Petrie, Christian M.
|
|
|
211 |
C |
p.
|
artikel
|
| 32 |
Data assimilation of turbulent flow in a large-scale steam generator: Part I- Iterative ensemble-Kalman filter-based reconstruction
|
Li, Sen
|
|
|
211 |
C |
p.
|
artikel
|
| 33 |
Deep heterogeneous joint architecture: A temporal frequency surrogate model for fuel performance codes
|
Zhou, Wenhan
|
|
|
211 |
C |
p.
|
artikel
|
| 34 |
Design and submersion criticality safety analysis of a space gas-cooled reactor with an in-core reactivity control structure doped with spectral shift absorbers
|
Chen, Zhiqi
|
|
|
211 |
C |
p.
|
artikel
|
| 35 |
Design of a prismatic CERMET megawatt gas-cooled reactor(PC-MGCR) for deep space exploration
|
Fan, Yuhan
|
|
|
211 |
C |
p.
|
artikel
|
| 36 |
Development and verification of an efficient collision algorithm for seismic analysis of fast reactor core assemblies
|
Zhou, Shi-An
|
|
|
211 |
C |
p.
|
artikel
|
| 37 |
Development and verification of an MC/MOC two-step scheme for neutronic analysis of FCM-fueled micro gas-cooled reactor
|
Feng, Kuaiyuan
|
|
|
211 |
C |
p.
|
artikel
|
| 38 |
Development of a computational scheme based on the DRAGON5 code for the neutronic study of VVER-type reactor rods and assemblies
|
Richard, Cyprien
|
|
|
211 |
C |
p.
|
artikel
|
| 39 |
Development of a conservative safety demonstration for loss of forced flow events in MYRRHA
|
Hamidouche, Tewfik
|
|
|
211 |
C |
p.
|
artikel
|
| 40 |
Development of active and passive reactivity control systems for a fast spectrum small modular reactor
|
Farid Khandaq, Muhammad
|
|
|
211 |
C |
p.
|
artikel
|
| 41 |
Development of a design method for burnable poisons in small modular fast reactors
|
Wu, Yiwei
|
|
|
211 |
C |
p.
|
artikel
|
| 42 |
Development of a friction factor correlation for a foam flow in a horizontal circular pipe
|
Lee, Hyoin
|
|
|
211 |
C |
p.
|
artikel
|
| 43 |
Development of a Griffin model of the advanced test reactor
|
Nguyen, Khang H.N.
|
|
|
211 |
C |
p.
|
artikel
|
| 44 |
Development of mechanistic model for CHF based on boiling crisis process
|
Liu, Haidong
|
|
|
211 |
C |
p.
|
artikel
|
| 45 |
Development of system analysis code and its application in transient simulation of supercritical CO2 Brayton cycle direct cooled reactors
|
Wu, Haijie
|
|
|
211 |
C |
p.
|
artikel
|
| 46 |
Dynamic simulation of core power control for SPWR based on dynamic model bank
|
Li, Zheng
|
|
|
211 |
C |
p.
|
artikel
|
| 47 |
Editorial Board
|
|
|
|
211 |
C |
p.
|
artikel
|
| 48 |
Effects of increasing the gap ratio on performance and pressure pulsations in a mixed-flow reactor coolant pump
|
Liu, Lei
|
|
|
211 |
C |
p.
|
artikel
|
| 49 |
Enhancing the neutronic performance of SMART Small modular reactor using alternative fuel material
|
Widiawati, Nina
|
|
|
211 |
C |
p.
|
artikel
|
| 50 |
Estimating parameter uncertainty bounds of human error probability using Monte Carlo simulation
|
Kim, Yochan
|
|
|
211 |
C |
p.
|
artikel
|
| 51 |
European research reactor strategy derived in the scope of the towards optimized use of research reactors (TOURR) project
|
Pungerčič, Anže
|
|
|
211 |
C |
p.
|
artikel
|
| 52 |
Evaluating uncertainties: Heat transfer parameter effects on stratified melt pool simulation
|
Guo, Pengya
|
|
|
211 |
C |
p.
|
artikel
|
| 53 |
Excitation functions for fast neutron induced reactions on Al, Zr, In and Au
|
Liu, B.
|
|
|
211 |
C |
p.
|
artikel
|
| 54 |
Experimental investigations and inverse heat transfer analysis to study heat transfer and ablation behaviour of concrete exposed to oxyacetylene flame
|
Jayakrishna, Pedduri
|
|
|
211 |
C |
p.
|
artikel
|
| 55 |
Experimental research on wash-down of insoluble aerosols with condensate on the vertical wall
|
Sun, Qingyang
|
|
|
211 |
C |
p.
|
artikel
|
| 56 |
Experimental study on CHF enhancement of different oxidized surfaces of low carbon steel in nanofluid
|
Li, Xiaojia
|
|
|
211 |
C |
p.
|
artikel
|
| 57 |
Experimental study on onset of nucleate boiling in wide-ranged parameters for narrow rectangular channels
|
Kuang, Bo
|
|
|
211 |
C |
p.
|
artikel
|
| 58 |
Experimental study on the plate-type fuel melting behavior based on alternative materials
|
Wu, Zhiyuan
|
|
|
211 |
C |
p.
|
artikel
|
| 59 |
Extending the finite elements neutronic code FENNECS to the Discontinuous Galerkin method
|
Henry, Romain
|
|
|
211 |
C |
p.
|
artikel
|
| 60 |
Fault diagnosis and degree evaluation of steam generator heat transfer tube rupture based on hybrid method
|
Jiang, Yingying
|
|
|
211 |
C |
p.
|
artikel
|
| 61 |
Flow distribution analysis of annular fuel with spacer grid
|
Wang, Sipeng
|
|
|
211 |
C |
p.
|
artikel
|
| 62 |
Flow-heat coupling analysis of the 1/4 symmetrical CAP1400 nuclear island loop based on the source term approach
|
Lu, Yeming
|
|
|
211 |
C |
p.
|
artikel
|
| 63 |
Framework for the correct treatment of model input parameters for Bayesian updating problems in nuclear engineering
|
Jędrzejczyk, Michał
|
|
|
211 |
C |
p.
|
artikel
|
| 64 |
Fuel performance modelling of Cr-coated Zircaloy cladding under DBA/LOCA conditions
|
Aragón, Pau
|
|
|
211 |
C |
p.
|
artikel
|
| 65 |
Generation and validation of a new WIMS-D library based on ENDF/B-VIII.0
|
Malec, Jan
|
|
|
211 |
C |
p.
|
artikel
|
| 66 |
Griffin: A MOOSE-based reactor physics application for multiphysics simulation of advanced nuclear reactors
|
Wang, Yaqi
|
|
|
211 |
C |
p.
|
artikel
|
| 67 |
Hermite methods for multi-energy group neutron kinetics model via quasi-static approach and piecewise functions
|
Aboanber, Ahmed E.
|
|
|
211 |
C |
p.
|
artikel
|
| 68 |
High-fidelity multiphysics modeling of pulsed reactor heat generation in the Annular Core Research Reactor fuel using Serpent 2
|
Colvin, Emory
|
|
|
211 |
C |
p.
|
artikel
|
| 69 |
HZP and HFP rod ejection analysis in a SMART-like reactor model using the GUARDYAN-SUBCHANFLOW coupled code system
|
Pázmán, Előd
|
|
|
211 |
C |
p.
|
artikel
|
| 70 |
Improvement of Geant4 Neutron-HP package: Unresolved resonance region description with probability tables
|
Zmeškal, M.
|
|
|
211 |
C |
p.
|
artikel
|
| 71 |
Improvement of the determination of radioactivity concentrations of short-lived radioisotopes with the time-dependent leakage model of VVER-type nuclear reactor
|
Szarvas, Csongor Kristóf
|
|
|
211 |
C |
p.
|
artikel
|
| 72 |
Insights into calculating Reference Discontinuity Factors with Serpent Monte Carlo code
|
Fridman, Emil
|
|
|
211 |
C |
p.
|
artikel
|
| 73 |
Intergranular fracture induced by helium bubbles segregation in NiFe single-phase concentrated solid solution alloys
|
Li, Jie
|
|
|
211 |
C |
p.
|
artikel
|
| 74 |
Investigation on cross-flow characteristics of two different mixing vane grid in a 5 × 5 rod bundle
|
Jiang, Li
|
|
|
211 |
C |
p.
|
artikel
|
| 75 |
Investigation on radioisotopes evolution in the fuel of Lead-Bismuth eutectic (LBE) cooled SPARK-NC core
|
Raza, Sohail Ahmad
|
|
|
211 |
C |
p.
|
artikel
|
| 76 |
KPCA-based fault detection and diagnosis model for the chemical and volume control system in nuclear power plants
|
Sun, Yiqian
|
|
|
211 |
C |
p.
|
artikel
|
| 77 |
Layered target design method for global spectrum optimization of radioisotope production
|
Xin, Yu
|
|
|
211 |
C |
p.
|
artikel
|
| 78 |
Loss-of-heat-sink transient simulation with RELAP5/Mod3.3 code for the ATHENA facility
|
Del Moro, T.
|
|
|
211 |
C |
p.
|
artikel
|
| 79 |
Machine-learned force fields for thermal neutron scattering law evaluations
|
Wormald, J.L.
|
|
|
211 |
C |
p.
|
artikel
|
| 80 |
Malfunction diagnosis based on residence time distribution of radiotracer signals in industrial processes using machine learning techniques
|
El_Tokhy, Mohamed S.
|
|
|
211 |
C |
p.
|
artikel
|
| 81 |
Measurement of gamma field inside the biological concrete shielding of VVER-1000 Mock-Up at the LR-0 reactor
|
Czakoj, Tomáš
|
|
|
211 |
C |
p.
|
artikel
|
| 82 |
Modelling research and performance analysis on a megawatt-level helium-xenon gas cooled small reactor based on the thermal-hydraulic constraints
|
Ju, Wenxuan
|
|
|
211 |
C |
p.
|
artikel
|
| 83 |
Monte Carlo based absolute efficiency calibration of power reactor spent fuel NDA measurements
|
Kirchknopf, Péter
|
|
|
211 |
C |
p.
|
artikel
|
| 84 |
Multi-objective optimization design of double-hooked corrugated plate dryer based on NSGA-II
|
Shuting, Zhong
|
|
|
211 |
C |
p.
|
artikel
|
| 85 |
Multi-zone cooperative reconstruction network for off-situ monitoring of the core neutron field
|
Cao, Pei
|
|
|
211 |
C |
p.
|
artikel
|
| 86 |
Negative flux fixups using positivity-preserving limiters for S N -discontinuous finite element scheme of neutron transport equation on unstructured triangular meshes
|
Ni, Dai
|
|
|
211 |
C |
p.
|
artikel
|
| 87 |
Neutronics analysis of a research reactor using a two-step method with the superhomogenization method
|
Luo, Chixu
|
|
|
211 |
C |
p.
|
artikel
|
| 88 |
Neutron spectrum measurements inside a self-shielded cyclotron during 18F production using a single-cylindrical neutron spectrometer with gold and indium activation foils
|
Tursinah, Rasito
|
|
|
211 |
C |
p.
|
artikel
|
| 89 |
Neutron transmission measurements for silica glass at the KURNS-LINAC
|
Lee, Jaehong
|
|
|
211 |
C |
p.
|
artikel
|
| 90 |
Nuclear data uncertainty propagation in continuous-energy Monte Carlo calculations
|
Aures, Alexander
|
|
|
211 |
C |
p.
|
artikel
|
| 91 |
Nuclear safety characterisation of PBX explosives under low-velocity impact conditions
|
Guo, Xiaohui
|
|
|
211 |
C |
p.
|
artikel
|
| 92 |
Nuclide number density prediction in the lattice physics calculation based on Dynamic mode decomposition
|
Qin, Shuai
|
|
|
211 |
C |
p.
|
artikel
|
| 93 |
Numerically efficient determination of kinetic parameters of the VR-1 nuclear reactor based on experimental data and ODE-constrained optimization
|
Strachota, Pavel
|
|
|
211 |
C |
p.
|
artikel
|
| 94 |
Numerical study on cavity-vortex evolution in cavitation flow in nuclear control valves with different openings and structural parameters
|
Xu, Xiaogang
|
|
|
211 |
C |
p.
|
artikel
|
| 95 |
Numerical study on the characteristics of the LBE thermal stratification in a scaled-down hot pool
|
Li, Wenbo
|
|
|
211 |
C |
p.
|
artikel
|
| 96 |
Numerical study on the thermal hydraulic characteristics of ERVC system
|
Huang, Yujian
|
|
|
211 |
C |
p.
|
artikel
|
| 97 |
On the convergence of the fixed point method for solving neutron transport alpha eigenvalue problems
|
Chang, Britton
|
|
|
211 |
C |
p.
|
artikel
|
| 98 |
On the Neutron Kinetics during a Promptcritical Accident in a Heavy Liquid Metal Fast Reactor and the Importance of Low-Energy Neutrons
|
Petrović, Đ.
|
|
|
211 |
C |
p.
|
artikel
|
| 99 |
Optimized utilization of neural networks for online efficiency monitoring and fault detection in PWR nuclear power plant
|
Arshad, Furqan
|
|
|
211 |
C |
p.
|
artikel
|
| 100 |
Parallel rCMFD acceleration method for the Triangular-Z nodal transport calculation of fast reactors
|
Xu, Zhi-Tao
|
|
|
211 |
C |
p.
|
artikel
|
| 101 |
Phase-field simulation of recrystallization and calculation of the effective thermal conductivity of polycrystalline UO2
|
Jiang, Yanbo
|
|
|
211 |
C |
p.
|
artikel
|
| 102 |
Physics analysis and design of heavy water reflected thermal test reactor
|
Hiruta, Hikaru
|
|
|
211 |
C |
p.
|
artikel
|
| 103 |
Power distribution bias from equilibrium xenon effects when insufficient neutron histories per cycle are used in Monte Carlo simulation of CANDU6
|
Seo, Yeseul
|
|
|
211 |
C |
p.
|
artikel
|
| 104 |
Prediction of the evolution of the nuclear reactor core parameters using artificial neural network
|
Palmi, Krzysztof
|
|
|
211 |
C |
p.
|
artikel
|
| 105 |
Preliminary exploration of liquid metals turbulent heat flux model based on OpenFOAM solver: Second-order differential heat flux model
|
Guo, Yuefeng
|
|
|
211 |
C |
p.
|
artikel
|
| 106 |
Pressurized water reactor fuel corrosion-related unidentified deposit and its related safety issues – II. Corrosion product deposition and heat transfer modeling
|
Liu, Yan
|
|
|
211 |
C |
p.
|
artikel
|
| 107 |
Radiation shielding properties of sustainable concrete with novel plastering techniques
|
Ali, Mohamed A.E.M.
|
|
|
211 |
C |
p.
|
artikel
|
| 108 |
Radioactive study of oxidation-corrosion materials activated by neutron in lead-bismuth eutectic reactors
|
Chen, Jiajie
|
|
|
211 |
C |
p.
|
artikel
|
| 109 |
Reduced order models for thermal hydraulic transient analysis in nuclear engineering
|
Bang, Young Suk
|
|
|
211 |
C |
p.
|
artikel
|
| 110 |
Research on core thermal hydraulic parameters prediction based on the improved GAN method and combined ANN model
|
Yuhan, Zhu
|
|
|
211 |
C |
p.
|
artikel
|
| 111 |
Research on fluid flow and heat transfer characteristics in a three-dimensional condenser
|
Duan, Zhiqiang
|
|
|
211 |
C |
p.
|
artikel
|
| 112 |
Research on simulation of hydrogen diffusion behavior based on CONTHAC-3D code
|
Chang, Yuan
|
|
|
211 |
C |
p.
|
artikel
|
| 113 |
Research on the high-performance computing method for the neutron diffusion spatiotemporal kinetics equation based on the convolutional neural network
|
Li, Xiangyu
|
|
|
211 |
C |
p.
|
artikel
|
| 114 |
Research on the key design of emergency core cooling scheme for Tsinghua high flux reactor
|
Wang, Zhuang
|
|
|
211 |
C |
p.
|
artikel
|
| 115 |
Retention analysis of aerosol inside narrow channels of the containment
|
Dandi, Zhang
|
|
|
211 |
C |
p.
|
artikel
|
| 116 |
Risk-effective optimal maintenance regime for a periodically tested safety component subjected to imperfect repair
|
Parsaei, S.
|
|
|
211 |
C |
p.
|
artikel
|
| 117 |
Semi-analytical solutions of fractional neutron diffusion models with thermal–hydraulic feedback via computational method
|
Hamada, Yasser Mohamed
|
|
|
211 |
C |
p.
|
artikel
|
| 118 |
Software-Based automation of burnup calculations for the NUR research reactor using SCALE/TRITON T6-DEPL sequence
|
Lababsa, Djahid
|
|
|
211 |
C |
p.
|
artikel
|
| 119 |
Stability and bifurcation analysis of a Sodium-cooled Fast Reactor under two-phase flow using 1D multiphysics model
|
Abbé, R.
|
|
|
211 |
C |
p.
|
artikel
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