| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A comparison of three algorithms applied in thermal-hydraulics and neutronics codes coupling for lbe-cooled fast reactor
|
Yang, Dongmei
|
|
|
149 |
C |
p.
|
artikel
|
| 2 |
A data-driven strategy for xenon dynamical forecasting using dynamic mode decomposition
|
Gong, Helin
|
|
|
149 |
C |
p.
|
artikel
|
| 3 |
A modified unscented transformation method for uncertainty propagation in neutron induced cross section measurement
|
Matharu, Jagjit Singh
|
|
|
149 |
C |
p.
|
artikel
|
| 4 |
Analysis of EBR-II pump run-up test with a best estimate plus uncertainty approach
|
Jeong, H.-Y.
|
|
|
149 |
C |
p.
|
artikel
|
| 5 |
Analysis of the drop dynamics of control rod assembly in a LBE-cooled research reactor
|
Arthur, Emmanuel Maurice
|
|
|
149 |
C |
p.
|
artikel
|
| 6 |
A new and rigorous SPN theory – Part IV: Numerical qualification of G S P 3 ( 0 ) and the generalized transverse integration nodal method
|
Chao, Yung-An
|
|
|
149 |
C |
p.
|
artikel
|
| 7 |
A POD reduced-order model for resolving the neutron transport problems of nuclear reactor
|
Sun, Yue
|
|
|
149 |
C |
p.
|
artikel
|
| 8 |
Application of deep neural network for generating resonance self-shielded cross-section
|
Qin, Shuai
|
|
|
149 |
C |
p.
|
artikel
|
| 9 |
A probabilistic model-based diagnostic framework for nuclear engineering systems
|
Nguyen, Tat Nghia
|
|
|
149 |
C |
p.
|
artikel
|
| 10 |
A sequential conjugate gradient method to estimate heat flux for nonlinear inverse heat conduction problem
|
Xiong, Ping
|
|
|
149 |
C |
p.
|
artikel
|
| 11 |
Decontamination of concrete waste from nuclear power plant decommissioning in South Korea
|
Han, Sangsoo
|
|
|
149 |
C |
p.
|
artikel
|
| 12 |
Development of a method for quantifying relative importance of NPP cyber attack probability variables based on factor analysis and AHP
|
Kim, Yong Sik
|
|
|
149 |
C |
p.
|
artikel
|
| 13 |
Editorial Board
|
|
|
|
149 |
C |
p.
|
artikel
|
| 14 |
Effect of debris combination on flow resistance of fuel assemblies
|
Liang, Ruixian
|
|
|
149 |
C |
p.
|
artikel
|
| 15 |
Evaluation of multi-cycle physics and economics considering end cycle optimization for a PWR
|
Son, Seungbeom
|
|
|
149 |
C |
p.
|
artikel
|
| 16 |
Experimental investigations on penetration failure by tube ejection for an APR1400 ICI nozzle during a severe accident
|
An, Sang Mo
|
|
|
149 |
C |
p.
|
artikel
|
| 17 |
Experimentally investigating phase separation and pressure drop as bubbly flow in a vertical branching T-junction
|
Wang, J.R.
|
|
|
149 |
C |
p.
|
artikel
|
| 18 |
Experimental study on local fuel–coolant interaction in molten pool with different melts
|
Cheng, Songbai
|
|
|
149 |
C |
p.
|
artikel
|
| 19 |
Fast solution of neutron diffusion problem with movement of control rods
|
Helin, Gong
|
|
|
149 |
C |
p.
|
artikel
|
| 20 |
Flow-induced acoustic resonances in closed tandem side branches with large diameter
|
Xiao, Yao
|
|
|
149 |
C |
p.
|
artikel
|
| 21 |
Geometric sensitivity analysis of generalized response function with RMC code
|
Shi, Guanlin
|
|
|
149 |
C |
p.
|
artikel
|
| 22 |
Heat pipe failure accident analysis in megawatt heat pipe cooled reactor
|
Ma, Yugao
|
|
|
149 |
C |
p.
|
artikel
|
| 23 |
Implementation of an adaptive energy grid routine in NDEX for the processing of thermal neutron scattering cross sections
|
Wormald, J.L.
|
|
|
149 |
C |
p.
|
artikel
|
| 24 |
Improvement of the uncertainty method with model treatment and optimized global sensitivity analysis and its application to pressurized water reactor
|
Xiong, Qingwen
|
|
|
149 |
C |
p.
|
artikel
|
| 25 |
Integral effect test results on the effect of asymmetric supply of feedwater during a station blackout transient of pressurized water reactor
|
Kang, Kyoung-Ho
|
|
|
149 |
C |
p.
|
artikel
|
| 26 |
Interpretation of the JANUS Phase 7 shielding experiment with TRIPOLI-4® and quantification of uncertainties due to nuclear data
|
Hajji, Amine
|
|
|
149 |
C |
p.
|
artikel
|
| 27 |
Investigation on long-term daily load follow operation capability of soluble boron-free SMR
|
Jo, Bum Hee
|
|
|
149 |
C |
p.
|
artikel
|
| 28 |
Linear stability analysis of RELAP5 two-fluid model in nuclear reactor safety results
|
Saraswat, S.P.
|
|
|
149 |
C |
p.
|
artikel
|
| 29 |
Linking classical PRA models to a dynamic PRA
|
Mandelli, D.
|
|
|
149 |
C |
p.
|
artikel
|
| 30 |
Long-term thermal aging performance of welding structures in primary coolant pipes for nuclear power plants
|
Fan, Minyu
|
|
|
149 |
C |
p.
|
artikel
|
| 31 |
Loose parts detection method combining blind deconvolution with support vector machine
|
Meng, Jianlin
|
|
|
149 |
C |
p.
|
artikel
|
| 32 |
Measurement of Høgdahl neutron flux parameters in the SM1 subcritical reactor of the University of Pavia
|
Di Luzio, M.
|
|
|
149 |
C |
p.
|
artikel
|
| 33 |
Modeling and simulation of feedwater control system with multiple once-through steam generators in a sodium-cooled fast reactor (II): Control system simulation
|
Sun, Peiwei
|
|
|
149 |
C |
p.
|
artikel
|
| 34 |
Multi-group equivalence in subgroup method based on generalized equivalence theory
|
Asim Shahzad, Muhammad
|
|
|
149 |
C |
p.
|
artikel
|
| 35 |
Neutronics design for molten salt accelerator-driven system as TRU burner
|
Sugawara, Takanori
|
|
|
149 |
C |
p.
|
artikel
|
| 36 |
On the nuclear safety improvement by post-inerting small modular reactor with stainless steel cladding
|
Avelar, Alan Matias
|
|
|
149 |
C |
p.
|
artikel
|
| 37 |
Population-based variance reduction for dynamic Monte Carlo
|
Legrady, David
|
|
|
149 |
C |
p.
|
artikel
|
| 38 |
Prediction of critical heat flux using Gaussian process regression and ant colony optimization
|
Jiang, B.T.
|
|
|
149 |
C |
p.
|
artikel
|
| 39 |
Research on fast intelligence multi-objective optimization method of nuclear reactor radiation shielding
|
Song, Yingming
|
|
|
149 |
C |
p.
|
artikel
|
| 40 |
Sensitivity and uncertainty analysis for the UAM-SFR sub-exercises with linear regression from random sampling
|
Zwermann, Winfried
|
|
|
149 |
C |
p.
|
artikel
|
| 41 |
Similarity analysis of thermal-fluid flow for thermal testing using scaled-down model of spent fuel storage cask
|
Lee, Ju-Chan
|
|
|
149 |
C |
p.
|
artikel
|
| 42 |
SMART with Trans-Critical CO2 power conversion system for maritime propulsion in Northern Sea Route, part 1: System design
|
Oh, Bong Seong
|
|
|
149 |
C |
p.
|
artikel
|
| 43 |
Stability analysis of nuclear-coupled thermal hydraulics for a natural circulation lead-cooled fast reactor
|
Lu, Qiyue
|
|
|
149 |
C |
p.
|
artikel
|
| 44 |
Stability analysis of predictor-corrector schemes for coupling neutronics and depletion
|
Cosgrove, P.
|
|
|
149 |
C |
p.
|
artikel
|
| 45 |
Sub-channel code development of lead-bismuth eutectic fast reactor available for multiple fuel assembly structures
|
Deng, Jian
|
|
|
149 |
C |
p.
|
artikel
|
| 46 |
The development of spallation target and fuel handling system for China initiative accelerator driven system
|
Li, Jin-Yang
|
|
|
149 |
C |
p.
|
artikel
|
| 47 |
The opportunities and challenges of micro heat piped cooled reactor system with high efficiency energy conversion units
|
Wang, D.Q.
|
|
|
149 |
C |
p.
|
artikel
|
| 48 |
Two-phase modeling of water-air flow of dispersed and segregated flows
|
Godino, Dario M.
|
|
|
149 |
C |
p.
|
artikel
|
Tijdschrift beschrijving