| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A Data-driven approach to predicting neutron penetration through media
|
Weiss, Abdullah G.
|
|
|
192 |
C |
p.
|
artikel
|
| 2 |
Additional axial decomposition parallelism for MOC solver in the neutron transport code PANDAS-MOC
|
Tao, Shunjiang
|
|
|
192 |
C |
p.
|
artikel
|
| 3 |
Aerosol turbulent deposition characteristics under small and micro-scaled leakage paths
|
Hu, Peizheng
|
|
|
192 |
C |
p.
|
artikel
|
| 4 |
An approach for multi-objective optimization based on preliminary PSA and its applications for fusion reactors
|
Sun, Ming
|
|
|
192 |
C |
p.
|
artikel
|
| 5 |
An equilibrium core depletion algorithm for pebble-bed reactors in the Griffin code
|
Schunert, Sebastian
|
|
|
192 |
C |
p.
|
artikel
|
| 6 |
A novel method for calculating annular fuel cell resonance effective temperature
|
Xiao, Yingjie
|
|
|
192 |
C |
p.
|
artikel
|
| 7 |
A scaling method based on the density variation for natural circulation in lead cooled fast reactors
|
Liu, Daxiao
|
|
|
192 |
C |
p.
|
artikel
|
| 8 |
Assessing parallel path cooling tower performance via artificial neural networks
|
Katinas, Christopher
|
|
|
192 |
C |
p.
|
artikel
|
| 9 |
Assessing spill fire characteristics through machine learning analysis
|
Sahin, Elvan
|
|
|
192 |
C |
p.
|
artikel
|
| 10 |
Benchmarking FFTF LOFWOS Test# 13 using SAM code: Baseline model development and uncertainty quantification
|
Liu, Yang
|
|
|
192 |
C |
p.
|
artikel
|
| 11 |
Challenges to the integrity of calandria, the CANDU PHWR moderator vessel, under serious accident loads and consequences of its failure
|
Nijhawan, Sunil
|
|
|
192 |
C |
p.
|
artikel
|
| 12 |
Climate adaptation in the spent fuel storage and disposal facilities: A literature review
|
Pizarro, J.
|
|
|
192 |
C |
p.
|
artikel
|
| 13 |
Comparative thermo-hydraulic study of different nuclear spent fuel cask designs using CFD codes
|
Hernandez-Avellaneda, Andres
|
|
|
192 |
C |
p.
|
artikel
|
| 14 |
Concept design and neutronics analysis of a heat pipe cooled nuclear reactor with CERMET fuel
|
Guo, Xiaoyu
|
|
|
192 |
C |
p.
|
artikel
|
| 15 |
Corrigendum to: “Physics-informed neural networks for the point kinetics equations for nuclear reactor dynamics” [Ann. Nucl. Energy 167 (2021) 108833]
|
Schiassi, Enrico
|
|
|
192 |
C |
p.
|
artikel
|
| 16 |
Coupled module of radioactive waste analysis for CANDU reactor based on the Monte Carlo method
|
Yoo, Seung Uk
|
|
|
192 |
C |
p.
|
artikel
|
| 17 |
Coupling heat transfer study of liquid sodium and supercritical carbon dioxide in a PCHE straight channel based on a four-equation model
|
Su, Xing-Kang
|
|
|
192 |
C |
p.
|
artikel
|
| 18 |
Design and optimization of thermal insulation structure for high-temperature pipeline inside the lower tank wall
|
Zhang, Lei
|
|
|
192 |
C |
p.
|
artikel
|
| 19 |
Design feasibility and failure mode analysis for a HALEU-based Kilopower-class space power reactor
|
Lim, Hong-sik
|
|
|
192 |
C |
p.
|
artikel
|
| 20 |
Dynamic event tree analysis of a severe accident sequence in a boiling water reactor experiencing a cyberattack scenario
|
Glingler, T.
|
|
|
192 |
C |
p.
|
artikel
|
| 21 |
Editorial Board
|
|
|
|
192 |
C |
p.
|
artikel
|
| 22 |
Effect of non-uniform inflow on the internal flow and hydrodynamic characteristics of a small modular reactor coolant pump
|
Long, Yun
|
|
|
192 |
C |
p.
|
artikel
|
| 23 |
Effects of angles and shapes of a corner crack on the driving force at a set-in nozzle-cylinder in a PWR pressure vessel
|
Wang, Shuai
|
|
|
192 |
C |
p.
|
artikel
|
| 24 |
Effects of sparging gas entrainment on void and temperature coefficients in the Transatomic Power molten salt reactor core
|
Lee, Alvin J.H.
|
|
|
192 |
C |
p.
|
artikel
|
| 25 |
Efficient predictor of pressurized water reactor safety parameters by topological information embedded convolutional neural network
|
Hou, Muzhou
|
|
|
192 |
C |
p.
|
artikel
|
| 26 |
Experimental investigation of characteristics of tip leakage vortex cavitation-induced vibration of a pump
|
Gong, Bo
|
|
|
192 |
C |
p.
|
artikel
|
| 27 |
Experimental studies on active oxygen control performance of solid PbO mass exchanger in liquid lead–bismuth eutectic loop
|
Liang, Ruixian
|
|
|
192 |
C |
p.
|
artikel
|
| 28 |
Extension of the X2 VVER-1000 benchmark by a control rod cluster ejection exercise
|
Bilodid, Yuri
|
|
|
192 |
C |
p.
|
artikel
|
| 29 |
Fuel assemblies loading pattern optimization of pressurized water reactors using the trees social relations algorithm
|
Shams, Sajjad
|
|
|
192 |
C |
p.
|
artikel
|
| 30 |
Fuel lifetime extension for the KLT-40S small modular reactor by means of thorium-uranium fuel cycle
|
Beliavskii, S.
|
|
|
192 |
C |
p.
|
artikel
|
| 31 |
Implementation of chrome oxidation model into best-estimate system code for accident tolerant fuel
|
Lee, Dong-Young
|
|
|
192 |
C |
p.
|
artikel
|
| 32 |
Improvement of Geant4 Neutron-HP package: Doppler broadening of the neutron elastic scattering kernel
|
Zmeškal, M.
|
|
|
192 |
C |
p.
|
artikel
|
| 33 |
Incorporation of anisotropic scattering into Fourier moment expanded axial DGFEM SN based 2D/1D coupling method
|
Kong, Boran
|
|
|
192 |
C |
p.
|
artikel
|
| 34 |
Innovative and advanced fuel based on nuclear waste transuranic nuclides: An alternative fuel for TRIGA Mark II research reactor
|
Mira, Mohamed
|
|
|
192 |
C |
p.
|
artikel
|
| 35 |
Investigation of Campbell mode with automatic calibration operated in fission chamber-based neutron flux monitoring system on EAST
|
Yang, Li
|
|
|
192 |
C |
p.
|
artikel
|
| 36 |
Lubrication performance analysis of Lead-Bismuth Internal-Feedback bearings in the nuclear main pump system
|
Huang, Bin
|
|
|
192 |
C |
p.
|
artikel
|
| 37 |
Machine learning approaches to equilibrium burnup analysis for Molten Salt Reactor
|
Chen, Shuning
|
|
|
192 |
C |
p.
|
artikel
|
| 38 |
Methodology for the investigation of undeclared atmospheric releases of radionuclides: Application to recent radionuclide detections in Northern Europe from 2019 to 2022
|
Saunier, O.
|
|
|
192 |
C |
p.
|
artikel
|
| 39 |
Molecular dynamics simulation on the dissolution and diffusion characteristics of FeCrAl alloy in liquid LBE
|
Xie, Lu
|
|
|
192 |
C |
p.
|
artikel
|
| 40 |
Multiphysics analysis of fuel Fragmentation, Relocation, and dispersal Susceptibility–Part 2: High-Burnup Steady-State operating and fuel performance conditions
|
Hirschhorn, Jake
|
|
|
192 |
C |
p.
|
artikel
|
| 41 |
Multiphysics analysis of fuel fragmentation, relocation, and dispersal susceptibility–Part 3: Thermal hydraulic evaluation of large break LOCA under high-burnup conditions
|
Wysocki, Aaron
|
|
|
192 |
C |
p.
|
artikel
|
| 42 |
Neighbor-informed burnup correction for gadolinia depletion in pin-homogenized core calculation
|
Jeon, Seoyoon
|
|
|
192 |
C |
p.
|
artikel
|
| 43 |
Neutron multiplication and reactor kinetics parameters in stochastic media based on randomized noise functions
|
Jones, Brian
|
|
|
192 |
C |
p.
|
artikel
|
| 44 |
Nitrogen containing reductants for the corrosion control of alloys relevant to nuclear reactors
|
Kumar, Padma S.
|
|
|
192 |
C |
p.
|
artikel
|
| 45 |
Non-linear differential equation for reactivity monitoring
|
Noronha, Viviane L.
|
|
|
192 |
C |
p.
|
artikel
|
| 46 |
NTPSS-vPower: A model for system simulation of a nuclear thermal propulsion system
|
Qi, Zhichao
|
|
|
192 |
C |
p.
|
artikel
|
| 47 |
Numerical study on the heat transfer characteristics of a microchannel heat exchanger with liquid lead–bismuth eutectic and supercritical CO2 as working fluids
|
Liu, Hong
|
|
|
192 |
C |
p.
|
artikel
|
| 48 |
OpenMC interpretation and analysis of two series highly-enriched-uranium thermal-spectrum benchmarks for nuclear data validation
|
Wang, Tianxiang
|
|
|
192 |
C |
p.
|
artikel
|
| 49 |
Optimization method of burnable poison based on genetic algorithm and artificial neural network
|
Zou, Jian
|
|
|
192 |
C |
p.
|
artikel
|
| 50 |
Overview of multiphysics R&D activities at the CEA/IRESNE institute
|
Vaglio-Gaudard, Claire
|
|
|
192 |
C |
p.
|
artikel
|
| 51 |
Preliminary analysis focusing on in-vessel thermal hydraulics in loss-of-heat removal systems in a sodium-cooled fast reactor
|
Sonoda, H.
|
|
|
192 |
C |
p.
|
artikel
|
| 52 |
Reliability analysis of core power optimization control using Kalman filter for accelerator driven system based on reconfigurable computing
|
Li, Jin-Yang
|
|
|
192 |
C |
p.
|
artikel
|
| 53 |
Removing singularities in the Bateman radioactive transformation equations using partial fraction decomposition
|
Malovytsia, M.S.
|
|
|
192 |
C |
p.
|
artikel
|
| 54 |
Seismic fragility analysis of nuclear containment structure under chloride-induced reinforcing steel corrosion conditions
|
Jin, Song
|
|
|
192 |
C |
p.
|
artikel
|
| 55 |
Simulation of stratification phenomena with a spectral Fourier–Chebyshev method on the background of a lead-cooled fast reactor
|
Liu, Daxiao
|
|
|
192 |
C |
p.
|
artikel
|
| 56 |
Spent Nuclear Fuel passive gamma analysis and reproducibility: Application to SKB-50 assemblies
|
Solans, Virginie
|
|
|
192 |
C |
p.
|
artikel
|
| 57 |
Study of the TN24p dry cask cooling by heat pipes
|
Larriba, Samantha
|
|
|
192 |
C |
p.
|
artikel
|
| 58 |
Study on irradiation embrittlement behavior of reactor pressure vessels by machine learning methods
|
He, Wen-ke
|
|
|
192 |
C |
p.
|
artikel
|
| 59 |
Thermal-hydraulic CFD simulation of PWR 5 × 5 bowing fuel assembly
|
Wang, Boxue
|
|
|
192 |
C |
p.
|
artikel
|
| 60 |
Thermal-mechanical coupling characteristics and heat pipe failure analysis of heat pipe cooled space reactor
|
Jiao, Guanghui
|
|
|
192 |
C |
p.
|
artikel
|
| 61 |
Towards preliminary design calculations with TRANSURANUS for application of Hastelloy cladding material
|
de Lara, A.
|
|
|
192 |
C |
p.
|
artikel
|
| 62 |
Transient characteristics of typical design basis accidents in integrated small reactor NHR200-II using RELAP5 model
|
Wang, Qian
|
|
|
192 |
C |
p.
|
artikel
|
| 63 |
Uncertainty and sensitivity analysis of the ASTEC simulations results of a MBLOCA scenario in a generic KONVOI plant using the FSTC tool
|
Stakhanova, A.
|
|
|
192 |
C |
p.
|
artikel
|
| 64 |
Using optimal squared-off cascades instead of optimal square cascades to produce enriched uranium required for fresh fuel in the equilibrium cycle in power reactors
|
Mirmohammadi, S.L.
|
|
|
192 |
C |
p.
|
artikel
|
| 65 |
Verification and validation (V&V) for fast reactor system analysis code FASYS
|
Zhao, Y.
|
|
|
192 |
C |
p.
|
artikel
|
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