| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Actinide and non-actinide production from UO2 fuel in W-SMR: Effects of gadolinium burnable absorber
|
Uguru, Edwin Humphrey
|
|
|
137 |
C |
p.
|
artikel
|
| 2 |
A game-theoretic approach to nuclear fuel cycle transition analysis under uncertainty
|
Phathanapirom, U.B.
|
|
|
137 |
C |
p.
|
artikel
|
| 3 |
A loading pattern optimization method based on discrete differential evolution
|
Ding, Hui
|
|
|
137 |
C |
p.
|
artikel
|
| 4 |
A mechanistic bubble crowding model for predicting critical heat flux in subchannels of a bundle
|
Liu, Yang
|
|
|
137 |
C |
p.
|
artikel
|
| 5 |
A method for the calculation of the adjoint function in cold neutron sources and its applications
|
Márquez, Ariel
|
|
|
137 |
C |
p.
|
artikel
|
| 6 |
A MOC-based neutron kinetics model for noise analysis
|
Gammicchia, A.
|
|
|
137 |
C |
p.
|
artikel
|
| 7 |
An a posteriori residual-based spatial discretization error estimator for S N neutron transport
|
Hart, Nathan H.
|
|
|
137 |
C |
p.
|
artikel
|
| 8 |
A note on the Chisholm parameter equation in RELAP
|
Awad, M.M.
|
|
|
137 |
C |
p.
|
artikel
|
| 9 |
Assessment of head loss through LOCA-generated debris deposited in PWR fuel assemblies
|
Wang, Da
|
|
|
137 |
C |
p.
|
artikel
|
| 10 |
A time and frequency domain analysis of the effect of vibrating fuel assemblies on the neutron noise
|
Vidal-Ferràndiz, A.
|
|
|
137 |
C |
p.
|
artikel
|
| 11 |
Calculation of λ modes of the multi-group neutron transport equation using the discrete ordinates and Finite Difference Method
|
Morató, S.
|
|
|
137 |
C |
p.
|
artikel
|
| 12 |
Comparative analysis of coupling schemes of Monte Carlo burnup calculation in RMC
|
Li, Wanlin
|
|
|
137 |
C |
p.
|
artikel
|
| 13 |
Defect detection of nuclear fuel assembly based on deep neural network
|
Guo, Zhangpeng
|
|
|
137 |
C |
p.
|
artikel
|
| 14 |
Development of a model for thermal-hydraulic analysis of helically coiled tube once-through steam generator based on Modelica
|
Ding, Hao
|
|
|
137 |
C |
p.
|
artikel
|
| 15 |
DIAMOND – A Method of Characteristics neutron transport code using unstructured meshing
|
Jain, Lakshay
|
|
|
137 |
C |
p.
|
artikel
|
| 16 |
Editorial Board
|
|
|
|
137 |
C |
p.
|
artikel
|
| 17 |
Experimental study of droplet impacting on inclined wetted wall in corrugated plate separator
|
Chen, Bowen
|
|
|
137 |
C |
p.
|
artikel
|
| 18 |
Feasibility estimation of new mitigation system through causal inference analysis with functional model
|
Jeon, In Seop
|
|
|
137 |
C |
p.
|
artikel
|
| 19 |
Finite element analysis of the SiC/SiC composite clad deformation in the presence of spacer grids
|
Li, Wei
|
|
|
137 |
C |
p.
|
artikel
|
| 20 |
Improved adaptive variance reduction algorithm based on RMC code for deep penetration problems
|
Pan, Qingquan
|
|
|
137 |
C |
p.
|
artikel
|
| 21 |
Investigation on reverse flow characteristics in UTSGs with coupled heat transfer between primary and secondary sides
|
Li, Mingrui
|
|
|
137 |
C |
p.
|
artikel
|
| 22 |
Investigation on streamwise fluidelastic instability of a single flexible tube in rotated triangular tube array subjected to water and two-phase cross-flow
|
Tan, Tiancai
|
|
|
137 |
C |
p.
|
artikel
|
| 23 |
Linear active disturbance rejection control for pressurized water reactor power based on partial feedback linearization
|
Liu, Yuyan
|
|
|
137 |
C |
p.
|
artikel
|
| 24 |
Local dynamic analysis in boiling water reactor
|
Polo-Labarrios, M.A.
|
|
|
137 |
C |
p.
|
artikel
|
| 25 |
MAPPS: A stochastic computational tool for multi-path analysis of physical protection systems
|
Setiawan, Yanuar A.
|
|
|
137 |
C |
p.
|
artikel
|
| 26 |
Modelling the tapered geometry of real 3D unit cell of polish MARIA reactor in a rectangular prism diffusion code
|
Muszynski, Dominik
|
|
|
137 |
C |
p.
|
artikel
|
| 27 |
Modifications of the turbulent diffusion layer model for the condensation heat transfer under the presence of noncondensable gases
|
Lee, Jun-Yeob
|
|
|
137 |
C |
p.
|
artikel
|
| 28 |
Neutron clustering as a driver of Monte Carlo burn-up instability
|
Cosgrove, P.
|
|
|
137 |
C |
p.
|
artikel
|
| 29 |
New homogenised axial diffusion coefficients from lattice calculations
|
Ray, Sherly
|
|
|
137 |
C |
p.
|
artikel
|
| 30 |
Novel numerical solution to the fractional neutron point kinetic equation in nuclear reactor dynamics
|
Polo-Labarrios, M.A.
|
|
|
137 |
C |
p.
|
artikel
|
| 31 |
Nuclear cross-section adjustment based on the 2-D/1-D transport code KYADJ
|
Wu, Qu
|
|
|
137 |
C |
p.
|
artikel
|
| 32 |
Nuclear Power Plant accident identification system with “don’t know” response capability: Novel deep learning-based approaches
|
Pinheiro, Victor Henrique Cabral
|
|
|
137 |
C |
p.
|
artikel
|
| 33 |
Numerical investigation on performance of moisture separator by Lagrangian-Eulerian strategy: Physical mechanisms, theoretical models, and advanced algorithms
|
Zhang, Huang
|
|
|
137 |
C |
p.
|
artikel
|
| 34 |
Potential of FAST (floating absorber for safety at transient) as a solution for positive coolant temperature coefficient in sodium-cooled FAST reactors
|
Kim, Chihyung
|
|
|
137 |
C |
p.
|
artikel
|
| 35 |
Probabilistic safety assessment method for spent nuclear fuel road transportation
|
Tao, Longlong
|
|
|
137 |
C |
p.
|
artikel
|
| 36 |
Quantification of the differences introduced by nuclear fuel cycle simulators in advanced scenario studies
|
Skarbeli, A.V.
|
|
|
137 |
C |
p.
|
artikel
|
| 37 |
Radiation dose consequences of postulated limiting accidents in small modular reactors to inform emergency planning zone size requirements
|
Hummel, D.W.
|
|
|
137 |
C |
p.
|
artikel
|
| 38 |
Radiotoxicity of minor actinides in thermal, epithermal and fast TMSRs with very high burnup
|
Zhang, Ao
|
|
|
137 |
C |
p.
|
artikel
|
| 39 |
Research on code coupling method in severe accident simulator development
|
Cao, Ying
|
|
|
137 |
C |
p.
|
artikel
|
| 40 |
Research on the capacitance control rod position measurement sensor in NHR-200
|
Hu, Guang
|
|
|
137 |
C |
p.
|
artikel
|
| 41 |
Review on neutronic/thermal-hydraulic coupling simulation methods for nuclear reactor analysis
|
Wang, Jincheng
|
|
|
137 |
C |
p.
|
artikel
|
| 42 |
Sensitivity analysis based on Morris method of passive system performance under ocean conditions
|
Wang, Chenyang
|
|
|
137 |
C |
p.
|
artikel
|
| 43 |
Serpent/SUBCHANFLOW pin-by-pin coupled transient calculations for a PWR minicore
|
Ferraro, Diego
|
|
|
137 |
C |
p.
|
artikel
|
| 44 |
Solving nonlinear discretizations of S N transport calculations
|
Hackemack, Michael W.
|
|
|
137 |
C |
p.
|
artikel
|
| 45 |
Spatial power profiling method using visual information in reactors with optically transparent coolants
|
Hearne, Jason A.
|
|
|
137 |
C |
p.
|
artikel
|
| 46 |
Spectral analysis by direct and adjoint Monte Carlo methods
|
Vitali, Vito
|
|
|
137 |
C |
p.
|
artikel
|
| 47 |
Study on nonparametric statistic method applied to nuclear criticality safety analysis of spent fuel rack
|
Chen, Tian
|
|
|
137 |
C |
p.
|
artikel
|
| 48 |
The use of multi-objective optimization to improve the design process of nuclear power plant systems
|
Wilding, Paul R.
|
|
|
137 |
C |
p.
|
artikel
|
| 49 |
Transient thermal-hydraulic analysis for fuel assembly blockage accident by coupling CFD code with the neutron kinetics model
|
Wang, Lizhi
|
|
|
137 |
C |
p.
|
artikel
|
| 50 |
Uncertainty and sensitivity analysis of PWR mini-core transients in the presence of nuclear data uncertainty using non-parametric tolerance limits
|
Aures, A.
|
|
|
137 |
C |
p.
|
artikel
|
| 51 |
Uncertainty propagation analysis for control rod worth of PWR based on the statistical sampling method
|
Hao, Chen
|
|
|
137 |
C |
p.
|
artikel
|
| 52 |
Unstable characteristics of the heat transfer pipe in the drain tank
|
Wu, Xiangcheng
|
|
|
137 |
C |
p.
|
artikel
|
| 53 |
Verification of dry storage cask loading using monoenergetic photon sources
|
Miller, Cameron A.
|
|
|
137 |
C |
p.
|
artikel
|
| 54 |
Whole core analysis of the single-fluid double-zone thorium molten salt reactor (SD-TMSR)
|
Ashraf, O.
|
|
|
137 |
C |
p.
|
artikel
|
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