| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Addendum to [Giaccardi et al., 2024]: On the definition of the escape rate coefficient
|
Pizzocri, D.
|
|
|
208 |
C |
p.
|
artikel
|
| 2 |
Advances from R2CA project on reactor simulations for burst rod number evaluation during LOCA
|
Belon, Sébastien
|
|
|
208 |
C |
p.
|
artikel
|
| 3 |
A low order MOC-based synthetic acceleration scheme of the MOC neutron transport method for molten salt reactors
|
Dai, Ming
|
|
|
208 |
C |
p.
|
artikel
|
| 4 |
Analysis of nuclear reactions and material damage on neutron absorbers using the HANARO research reactor
|
Jeong, Hae Sun
|
|
|
208 |
C |
p.
|
artikel
|
| 5 |
Analysis of single bubble dynamics based on VOF method
|
Mei, Zhongkai
|
|
|
208 |
C |
p.
|
artikel
|
| 6 |
A new 181Ta neutron resolved resonance region evaluation
|
Barry, D.P.
|
|
|
208 |
C |
p.
|
artikel
|
| 7 |
Application of full-core three-dimensional multi-physics calculation to the EBR-II SHRT-45R benchmark
|
Luo, Chixu
|
|
|
208 |
C |
p.
|
artikel
|
| 8 |
Cascade control system design for a space nuclear reactor
|
Liu, Pinchao
|
|
|
208 |
C |
p.
|
artikel
|
| 9 |
Comparison of the results of conservative and realistic approaches to the analysis of radioactive release for LOCA of pressurized water VVER–440 and 1000 NPPs
|
Berezhnyi, A.
|
|
|
208 |
C |
p.
|
artikel
|
| 10 |
Conceptual design and analysis of a new plate-type fuel element for flattening of reactor power distribution
|
Feng, Zhiyuan
|
|
|
208 |
C |
p.
|
artikel
|
| 11 |
CORTEX experiments, Part II: Postprocessing of neutron noise time series to determine reliable mean and uncertainties
|
Ambrožič, Klemen
|
|
|
208 |
C |
p.
|
artikel
|
| 12 |
Creating formative HRA dependency models using the HRA dependency idioms and SACADA data, Part II: Model quantification
|
Paglioni, Vincent P.
|
|
|
208 |
C |
p.
|
artikel
|
| 13 |
Creating formative HRA dependency models using the HRA dependency idioms and SACADA data, Part I: Model construction algorithm
|
Paglioni, Vincent P.
|
|
|
208 |
C |
p.
|
artikel
|
| 14 |
Development and application of a refined subchannel analysis code for lead-based wire-wrapped bundles
|
Sun, Yubo
|
|
|
208 |
C |
p.
|
artikel
|
| 15 |
Editorial Board
|
|
|
|
208 |
C |
p.
|
artikel
|
| 16 |
Effect of neutron beamline irradiation on hydrogen equilibrium vapor pressure over hydrided Zircaloy-4
|
Luscher, W.G.
|
|
|
208 |
C |
p.
|
artikel
|
| 17 |
Efficient continuous Energy-Multigroup hybrid depletion scheme using the Shift Monte Carlo code. Part I: Energy condensation sensitivity analysis
|
Lujan, Vidor H.
|
|
|
208 |
C |
p.
|
artikel
|
| 18 |
Evaluating the impact of decay heat on repository footprint in nuclear fuel cycle scenarios: Introducing the BADGER code
|
Peakman, Aiden
|
|
|
208 |
C |
p.
|
artikel
|
| 19 |
Experimental study on hydraulic characteristics and throttle component selection for fuel rod irradiation test device
|
Zhao, Wenbin
|
|
|
208 |
C |
p.
|
artikel
|
| 20 |
Experimental study on the influence of initial state parameters on the start-up and heat transfer characteristics of separated heat pipe system
|
Zhou, Xinyu
|
|
|
208 |
C |
p.
|
artikel
|
| 21 |
Exploring the BaO/B2O3 substitution impacts on B2O3-ZnO-PbO-BaO glasses: Comprehensive analysis for physical, optical, mechanical, and radiation shielding properties
|
Sayyed, M.I.
|
|
|
208 |
C |
p.
|
artikel
|
| 22 |
Frictional pressure drop correlation of steam-water two-phase flow in helically coiled tubes
|
Su, Yuqing
|
|
|
208 |
C |
p.
|
artikel
|
| 23 |
Generating optimal configurations for neutron source distribution in subcritical systems. A linear-programming approach
|
Moraes, Leonardo R.C.
|
|
|
208 |
C |
p.
|
artikel
|
| 24 |
Global Sensitivity Analysis for Segmented Inverse Uncertainty Quantification in the Safety Analysis of Nuclear Power Plants
|
Di Maio, Francesco
|
|
|
208 |
C |
p.
|
artikel
|
| 25 |
Identifying and overcoming deficiencies of nuclear data on the fission of light actinides by use of the GEF code
|
Schmidt, Karl-Heinz
|
|
|
208 |
C |
p.
|
artikel
|
| 26 |
Impact of experimental effects on a resolved resonance evaluation for practical applications
|
Leal, L.
|
|
|
208 |
C |
p.
|
artikel
|
| 27 |
Investigations of sodium droplet spreading and evaporation on surfaces with different wettability based on lattice Boltzmann simulations
|
Tang, Songsheng
|
|
|
208 |
C |
p.
|
artikel
|
| 28 |
Learning experimental data to predict fluid-elastic instability and optimize configuration of tube arrays
|
Zhao, Xielin
|
|
|
208 |
C |
p.
|
artikel
|
| 29 |
Low intensity radiation image restoration method based on Bayesian maximum posterior framework
|
Da, Tianxing
|
|
|
208 |
C |
p.
|
artikel
|
| 30 |
Model inadequacy in fuel performance code calibration: Derivative-based parameter uncertainty inflation
|
Robertson, Gustav
|
|
|
208 |
C |
p.
|
artikel
|
| 31 |
Modeling and validation of a water-cooled Reactor Cavity Cooling System (RCCS)
|
Gorman, Michael
|
|
|
208 |
C |
p.
|
artikel
|
| 32 |
Monte Carlo transport correction for graphite-moderated nuclear reactors using the Cumulative Migration Method
|
Liu, Zhaoyuan
|
|
|
208 |
C |
p.
|
artikel
|
| 33 |
MORPHEE a multiphysics tool for control rod withdrawal modeling in SFR
|
Jeannin, Marlène
|
|
|
208 |
C |
p.
|
artikel
|
| 34 |
Multi-dimensional simulation of the segmented thermoelectric generator applied in the heat pipe reactor based on COMSOL
|
Wu, Aoguang
|
|
|
208 |
C |
p.
|
artikel
|
| 35 |
Multilabel proportion prediction and out-of-distribution detection on gamma spectra of short-lived fission products
|
Van Omen, Alan
|
|
|
208 |
C |
p.
|
artikel
|
| 36 |
Multi-physics field coupling optimization study for U3Si2-Al arc-type fuel plate performance analysis
|
Feng, Zhiyuan
|
|
|
208 |
C |
p.
|
artikel
|
| 37 |
NECP-panda: A neutronics and thermal-hydraulic analysis code for pebble-bed high temperature gas-cooled reactor
|
Wu, Yuxuan
|
|
|
208 |
C |
p.
|
artikel
|
| 38 |
Nuclear data processing and benchmarking for the test edition of China evaluated photonuclear data library (CENDL/PD-b)
|
Liu, Ping
|
|
|
208 |
C |
p.
|
artikel
|
| 39 |
Nuclear data uncertainty quantification analysis at Studsvik Scandpower
|
Hykes, J.
|
|
|
208 |
C |
p.
|
artikel
|
| 40 |
Numerical insights into the transient behaviour of single-phase Natural Circulation Loops for nuclear passive cooling applications
|
Wilson, Dean
|
|
|
208 |
C |
p.
|
artikel
|
| 41 |
Numerical investigation on effects of fuel rod with the position of bow deformation on the flow and heat transfer of PWR
|
Li, Chengde
|
|
|
208 |
C |
p.
|
artikel
|
| 42 |
Numerical investigation on the effect of different factors on the flow-induced vibration of wire-wrapped fuel rod under axial flow
|
Guo, Hongjian
|
|
|
208 |
C |
p.
|
artikel
|
| 43 |
Numerical study on flow and heat transfer characteristics of liquid lithium in hexagonal rod bundle channels
|
Wang, Yue
|
|
|
208 |
C |
p.
|
artikel
|
| 44 |
Numerical study on heat transfer and flow oscillations of supercritical-pressure water in helical tubes
|
Liu, Mengmeng
|
|
|
208 |
C |
p.
|
artikel
|
| 45 |
Numerical validation of the APOLLO3®-FR deterministic calculation route based on a simplified Phenix configuration
|
Viallon, Victor
|
|
|
208 |
C |
p.
|
artikel
|
| 46 |
OFFBEAT V&V studies for REBEKA tests on cladding ballooning and burst during LOCA conditions
|
Verma, L.
|
|
|
208 |
C |
p.
|
artikel
|
| 47 |
Path planning of PRM based on artificial potential field in radiation environments
|
Zheng, Xiaochang
|
|
|
208 |
C |
p.
|
artikel
|
| 48 |
Physics-informed Reinforcement Learning optimization of PWR core loading pattern
|
Seurin, Paul
|
|
|
208 |
C |
p.
|
artikel
|
| 49 |
Possible criticality scenario and its mechanism of the Windscale Works criticality accident in 1970 analyzed by computational fluid dynamics and Monte Carlo neutron transport
|
Fukuda, Kodai
|
|
|
208 |
C |
p.
|
artikel
|
| 50 |
Pressurized water reactor fuel corrosion-related unidentified deposit and its related safety issues – I. Corrosion product deposition and heat transfer
|
Liu, Yan
|
|
|
208 |
C |
p.
|
artikel
|
| 51 |
Pressurized water reactor fuel corrosion-related unidentified deposit and its related safety issues – III. N-TH-M coupled CIPS prediction
|
Liu, Yan
|
|
|
208 |
C |
p.
|
artikel
|
| 52 |
Representation of multi-group cross section libraries and flux spectra for PWR materials with deep neural networks for lattice calculations
|
Chan, Yi Meng
|
|
|
208 |
C |
p.
|
artikel
|
| 53 |
Research on fault simulation and fault diagnosis of electric gate valves in nuclear power plants
|
Huang, Xue-Ying
|
|
|
208 |
C |
p.
|
artikel
|
| 54 |
Research on spherical harmonics method based on the MOC neutron transport code OpenMOC
|
Zhou, Feng
|
|
|
208 |
C |
p.
|
artikel
|
| 55 |
Research on the calculation method of neutron diffusion spatiotemporal kinetics equation based on the time series convolutional neural network
|
Li, Xiangyu
|
|
|
208 |
C |
p.
|
artikel
|
| 56 |
Research on the connection calculation of direct kinetics simulation and predictor-corrector Quasi-Static method based on RMC code
|
Jia, Conglong
|
|
|
208 |
C |
p.
|
artikel
|
| 57 |
Sensitivity and perturbation analysis of alpha-eigenvalue with time-dependent Monte Carlo perturbation techniques
|
Yamamoto, Toshihiro
|
|
|
208 |
C |
p.
|
artikel
|
| 58 |
Steady state neutronic and thermal–mechanical coupling analysis of inelastic deformation in solid-state heat pipe cooled reactor
|
Wang, Yong
|
|
|
208 |
C |
p.
|
artikel
|
| 59 |
Study and transient neutronics analysis of a 10kWth space heat pipe reactor based on a new dual protection control scheme with control annulus and movable radial reflector
|
Zhu, Shaoyang
|
|
|
208 |
C |
p.
|
artikel
|
| 60 |
Study on the safety performance of an offshore stationary lead-cooled fast reactor design loaded with nitride fuel
|
Meng, Lu
|
|
|
208 |
C |
p.
|
artikel
|
| 61 |
Study on the thermo-hydraulic behaviors within a CiADS 61-pin wire-wrapped fuel assembly under porous blockage conditions based on LBEblockageFoam
|
Li, Yun-Xiang
|
|
|
208 |
C |
p.
|
artikel
|
| 62 |
Subcooled boiling heat transfer characteristics and correlation development for narrow rectangular channels with a large aspect ratio under high-pressure conditions
|
Wang, Teng
|
|
|
208 |
C |
p.
|
artikel
|
| 63 |
Surrogate model for predicting severe accident progression in nuclear power plant using deep learning methods and Rolling-Window forecast
|
Lee, Yeonha
|
|
|
208 |
C |
p.
|
artikel
|
| 64 |
Survey of prospective techniques for molten salt reactor feed monitoring
|
Skutnik, Steve E.
|
|
|
208 |
C |
p.
|
artikel
|
| 65 |
The numerical investigation of the thermal–hydraulic behavior in a 3 × 3 rod bundle with spacer grids
|
Yang, Cheng
|
|
|
208 |
C |
p.
|
artikel
|
| 66 |
Theoretical model and optimization method research of flow and pressure fluctuation attenuation based on spring vibrator
|
Wang, Sipeng
|
|
|
208 |
C |
p.
|
artikel
|
| 67 |
Tribological behaviors and wettability evolution of phenolic resin-impregnated graphite materials under water immersion condition
|
Xu, Jimin
|
|
|
208 |
C |
p.
|
artikel
|
| 68 |
Validation of a three-dimensional two-phase code, CUPID, using a rod-bundle boiling test facility, SIRIUS-3D
|
Guk Jeon, Byong
|
|
|
208 |
C |
p.
|
artikel
|
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