| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Advanced fault diagnosis method for nuclear power plant based on convolutional gated recurrent network and enhanced particle swarm optimization
|
Wang, Hang
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|
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151 |
C |
p.
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artikel
|
| 2 |
Aerosol processing of glass for radioactive salt waste immobilization
|
Kang, Hyun Woo
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151 |
C |
p.
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artikel
|
| 3 |
A hybrid porous model for full reactor core scale CFD investigation of a prismatic HTGR
|
Wang, Chengqi
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151 |
C |
p.
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artikel
|
| 4 |
A linearized coarse mesh finite difference preconditioner for the within-group Krylov subspace iteration based on two-dimensional method of characteristics
|
Zhang, Guangchun
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151 |
C |
p.
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artikel
|
| 5 |
A method of dynamic homogenization: application to 2D core calculation
|
Galia, Antonio
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151 |
C |
p.
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artikel
|
| 6 |
Analysis of the impact of fuel microstructure on irradiation-enhanced densification using grand potential simulations
|
Greenquist, Ian
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151 |
C |
p.
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artikel
|
| 7 |
A new methodology to estimate stochastic uncertainty of MCNP-predicted isotope concentrations in nuclear fuel burnup simulations
|
Chirayath, Sunil S.
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151 |
C |
p.
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artikel
|
| 8 |
An improvement to the Kalos’ formula for double layer gamma ray exposure buildup factors for shielding materials of nuclear and radiological facilities
|
Basu, Pew
|
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151 |
C |
p.
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artikel
|
| 9 |
A porous medium model for simulating conjugate heat transfer between wire-wrapped fuel bundles under forced and mixed convection
|
Chen, Yutong
|
|
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151 |
C |
p.
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artikel
|
| 10 |
Application of complex-step derivative method for k-eigenvalue sensitivity calculation in neutron transport models
|
Wu, Zeyun
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151 |
C |
p.
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artikel
|
| 11 |
Application of PLC based smart microgrid controller for sequential load restoration during station blackout of nuclear power plants
|
Khatua, Subhakanta
|
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151 |
C |
p.
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artikel
|
| 12 |
Application of the augmented block Householder Arnoldi method to the calculation of non-fundamental modes of the diffusion equation
|
Hébert, Alain
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151 |
C |
p.
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artikel
|
| 13 |
A preliminary study on concrete ablation during ex-vessel cooling in pre-flooded Westinghouse 3-loop NPP reactor cavity
|
Na, Hanbee
|
|
|
151 |
C |
p.
|
artikel
|
| 14 |
A radionuclide outlier identification and correlation analysis on low- and intermediate-level radioactive waste
|
Jang, Sung-Chan
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|
|
151 |
C |
p.
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artikel
|
| 15 |
Assessment of management measures on station blackout accident in Unit-1 Bushehr nuclear power plant
|
Vahman, Navid
|
|
|
151 |
C |
p.
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artikel
|
| 16 |
Bubble coalescence, growth, breakup and distribution in boiling water-cooled packed bed reactor
|
Xu, Guangzhan
|
|
|
151 |
C |
p.
|
artikel
|
| 17 |
CFD analysis of thermal-hydraluic behaviors in a LBE cooled 19-pin wire wrapped bundle under porous lumped blockage conditions
|
Lyu, Kefeng
|
|
|
151 |
C |
p.
|
artikel
|
| 18 |
CFD simulation of thermal hydraulic phenomena in enclosed cavity of nuclear power plants
|
Chen, Chong
|
|
|
151 |
C |
p.
|
artikel
|
| 19 |
Characteristics and linear stability analysis of RELAP5 two-fluid model for two-component, two-phase flow
|
Saraswat, S.P.
|
|
|
151 |
C |
p.
|
artikel
|
| 20 |
Characteristics of liquid film rupture at wave plate corner: A short communication
|
Wang, Bo
|
|
|
151 |
C |
p.
|
artikel
|
| 21 |
Characterization of high-temperature nuclear fuel-coolant interactions through X-ray visualization and image processing
|
Johnson, Michael
|
|
|
151 |
C |
p.
|
artikel
|
| 22 |
Closed-loop experimental investigation of single-phase natural circulation flow phenomena based on temperature and heating power variations
|
Bello, Solomon
|
|
|
151 |
C |
p.
|
artikel
|
| 23 |
Comparison between passive reactor cavity cooling systems based on atmospheric radiation and atmospheric natural circulation
|
Takamatsu, Kuniyoshi
|
|
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151 |
C |
p.
|
artikel
|
| 24 |
Constrained Bayesian optimization of criticality experiments
|
Siefman, D.
|
|
|
151 |
C |
p.
|
artikel
|
| 25 |
Coupling one-dimensional user code and STAR-CCM+ for simulation of rolling conditions in a rod bundle channel
|
Zhang, Yinxing
|
|
|
151 |
C |
p.
|
artikel
|
| 26 |
Criticality benchmark of Monte Carlo code MCS for light water reactor fuel in transportation and storage packages
|
Lee, Hochul
|
|
|
151 |
C |
p.
|
artikel
|
| 27 |
Demonstration of prospective application of the dual number automatic differentiation for uncertainty propagation in neutronic calculations
|
Bokov, Pavel M.
|
|
|
151 |
C |
p.
|
artikel
|
| 28 |
Derivation of preliminary DCGL for Kori Unit 1 using RESRAD-OFFSITE and comparison with RESRAD-ONSITE
|
Park, Sang June
|
|
|
151 |
C |
p.
|
artikel
|
| 29 |
Design, simulation and reconstruction for a fast speed two-phase flow CT with 241Am gamma ray sources
|
Yan, Mingfei
|
|
|
151 |
C |
p.
|
artikel
|
| 30 |
Development of a bypass control strategy for supercritical CO2 Brayton cycle cooled reactor system under load-following operation
|
Gao, Chuntian
|
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|
151 |
C |
p.
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artikel
|
| 31 |
Development of a four-fluid model for condensing steam flows
|
Bolduc, CiCi P.
|
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151 |
C |
p.
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artikel
|
| 32 |
Development of a steady state analysis code for molten salt reactor based on nodal expansion method
|
Cui, Y.
|
|
|
151 |
C |
p.
|
artikel
|
| 33 |
Development of thermal hydraulic analysis code of annular fuel under flow blockage condition
|
Xia, Hang
|
|
|
151 |
C |
p.
|
artikel
|
| 34 |
Dynamic characteristics and scaling distortion of gravity-driven draining process in Core Makeup Tank
|
Li, Xiangbin
|
|
|
151 |
C |
p.
|
artikel
|
| 35 |
Dynamic models and control system design for heated channels in a Canadian SCWR
|
Han, Huirui
|
|
|
151 |
C |
p.
|
artikel
|
| 36 |
Editorial Board
|
|
|
|
151 |
C |
p.
|
artikel
|
| 37 |
Effect of par deactivation by carbon monoxide in the late phase of a severe accident
|
Klauck, M.
|
|
|
151 |
C |
p.
|
artikel
|
| 38 |
Effects of NaCl addition on magnetite deposition on the outer surfaces of steam generator tubes
|
Lee, Ji-Min
|
|
|
151 |
C |
p.
|
artikel
|
| 39 |
Estimation of system code SOCRAT/V3 accuracy to simulate the heat transfer in a pool of volumetrically heated liquid on the basis of BAFOND experiments
|
Dolzhenkov, E.A.
|
|
|
151 |
C |
p.
|
artikel
|
| 40 |
Evaluation of the MOC based on the Sanchez-Pomraning method for double heterogeneity system
|
Liang, Yuechao
|
|
|
151 |
C |
p.
|
artikel
|
| 41 |
Evolutionary simulated annealing for fuel loading optimization of VVER-1000 reactor
|
Tran, Viet-Phu
|
|
|
151 |
C |
p.
|
artikel
|
| 42 |
Experimental and numerical investigation on flow characteristics of inter-wrapper channel in LMFBR
|
Liang, Yu
|
|
|
151 |
C |
p.
|
artikel
|
| 43 |
Experimental and theoretical study of jet hydrodynamic breakup behavior with air entrainment
|
Chen, Jingtan
|
|
|
151 |
C |
p.
|
artikel
|
| 44 |
Experimental investigation on heat transfer characteristics of oxide layer of molten pool
|
Li, Zongyang
|
|
|
151 |
C |
p.
|
artikel
|
| 45 |
Experimental measurements to evaluate the effects of fuel microstructure on fission gas release in thoria
|
Barry, A.
|
|
|
151 |
C |
p.
|
artikel
|
| 46 |
Experimental research on the characteristics of steam jet condensation in subcooled water through a double-hole nozzle in one direction
|
Lu, Daogang
|
|
|
151 |
C |
p.
|
artikel
|
| 47 |
Experimental study of critical heat flux mechanism on a vertical heated surface under rolling motion
|
Albdour, Samah A.
|
|
|
151 |
C |
p.
|
artikel
|
| 48 |
Experimental study on flow modes and transient characteristics in low-pressure equal-height-difference natural circulation system
|
Sun, Jianchuang
|
|
|
151 |
C |
p.
|
artikel
|
| 49 |
Experimental study on heat transfer limit of high temperature potassium heat pipe for advanced reactors
|
Wang, Chenglong
|
|
|
151 |
C |
p.
|
artikel
|
| 50 |
Experimental study on the hydraulic characteristics of inertia tank after the failure of pump power
|
Wang, Gongqing
|
|
|
151 |
C |
p.
|
artikel
|
| 51 |
Experiments and simulation of helium breakdown at high pressure and temperature in a non-uniform electric field
|
You, Qi
|
|
|
151 |
C |
p.
|
artikel
|
| 52 |
Feasibility study on burnable poison credit concept to HTGR fuel fabrication from core specification perspective
|
Fukaya, Yuji
|
|
|
151 |
C |
p.
|
artikel
|
| 53 |
First order comprehensive adjoint sensitivity analysis methodology (1st-casam) for computing efficiently the exact response sensitivities for physical systems with imprecisely known boundaries and parameters: General theory and illustrative paradigm applications
|
Cacuci, Dan Gabriel
|
|
|
151 |
C |
p.
|
artikel
|
| 54 |
Geometry design and performance optimization of a terrestrial radioisotope thermoelectric generator based on finite element analysis
|
Deng, Wei
|
|
|
151 |
C |
p.
|
artikel
|
| 55 |
Global variance reduction method based on multi-group Monte Carlo adjoint calculation
|
Shi, Tao
|
|
|
151 |
C |
p.
|
artikel
|
| 56 |
Investigation of radiolysis in cement pastes immobilizing simulated evaporator concrentrates
|
Zatloukalová, Jaroslava
|
|
|
151 |
C |
p.
|
artikel
|
| 57 |
Kinetic methods in Monte Carlo code RMC and its implementation to C5G7-TD benchmark
|
Guo, Xiaoyu
|
|
|
151 |
C |
p.
|
artikel
|
| 58 |
Load-following control of nuclear reactors based on fuzzy input-output model
|
Luan, Xiuchun
|
|
|
151 |
C |
p.
|
artikel
|
| 59 |
Measurement, simulation and uncertainty quantification of the neutron flux at the McMaster Nuclear Reactor
|
MacConnachie, Elizabeth L.
|
|
|
151 |
C |
p.
|
artikel
|
| 60 |
Mechanism research of two-phase flow regimes during bottom reflooding in narrow rectangular channel
|
Xu, Wei
|
|
|
151 |
C |
p.
|
artikel
|
| 61 |
Modeling and neutronic analysis of pin-cell comprising nuclear fuel with different chemical composition and neutron moderator using Monte Carlo code OpenMC
|
Reza, Farshid
|
|
|
151 |
C |
p.
|
artikel
|
| 62 |
Modeling and validation of RELAP5 for natural circulation flow in a single PWR fuel assembly
|
Ni, Song
|
|
|
151 |
C |
p.
|
artikel
|
| 63 |
Modeling of oxidation of UO2 pellets
|
Abolpour, Bahador
|
|
|
151 |
C |
p.
|
artikel
|
| 64 |
NECP-MCX: A hybrid Monte-Carlo-Deterministic particle-transport code for the simulation of deep-penetration problems
|
He, Qingming
|
|
|
151 |
C |
p.
|
artikel
|
| 65 |
Neutronic and thermal-mechanical coupling analyses in a solid-state reactor using Monte Carlo and finite element methods
|
Ma, Yugao
|
|
|
151 |
C |
p.
|
artikel
|
| 66 |
Nodal Integral method for multi-group neutron diffusion equation in three dimensional cylindrical coordinate system
|
Raj, Manish
|
|
|
151 |
C |
p.
|
artikel
|
| 67 |
Numerical optimization of a multiphysics calculation scheme based on partial convergence
|
Cattaneo, Paolo
|
|
|
151 |
C |
p.
|
artikel
|
| 68 |
Numerical study on the heat transfer deterioration and its mitigations for supercritical CO2 flowing in a horizontal miniature tube
|
Eze, Chika
|
|
|
151 |
C |
p.
|
artikel
|
| 69 |
ONIX: An open-source depletion code
|
de Troullioud de Lanversin, J.
|
|
|
151 |
C |
p.
|
artikel
|
| 70 |
Operator action log based monitoring and control and its verification of nuclear power plants
|
Jang, Gwi-sook
|
|
|
151 |
C |
p.
|
artikel
|
| 71 |
Performance assessment of longitudinal flow through rod bundle of ETRR-2 Cobalt/Iridium irradiation device
|
Elbakhshawangy, Hesham
|
|
|
151 |
C |
p.
|
artikel
|
| 72 |
Phonon parameters fitting for the simulated Thermal-Neutron scattering cross section of H in ZrHx using Unified Monte Carlo method
|
Wang, Lipeng
|
|
|
151 |
C |
p.
|
artikel
|
| 73 |
Precise localization of neutron noise sources based on transport theory and comparison with diffusion theory
|
Bahrami, Mona
|
|
|
151 |
C |
p.
|
artikel
|
| 74 |
Preferred core conceptual design of pebble bed advanced high temperature reactor
|
Wang, Lianjie
|
|
|
151 |
C |
p.
|
artikel
|
| 75 |
Preliminary prediction for survival time of fuel rod under critical heat flux
|
He, Yanan
|
|
|
151 |
C |
p.
|
artikel
|
| 76 |
Quasi-Maxwellian Interference Term Functions
|
Guedes, Guilherme
|
|
|
151 |
C |
p.
|
artikel
|
| 77 |
Re-evaluation of level 2 PSA results of a VVER-1000 NPP with consideration of innovative severe accident management strategies
|
Mohsendokht, Massoud
|
|
|
151 |
C |
p.
|
artikel
|
| 78 |
Revisitation of the studies on covariance data and adjustment analysis: A tribute to M. Salvatores for his great works and remaining future tasks
|
Takeda, Toshikazu
|
|
|
151 |
C |
p.
|
artikel
|
| 79 |
Scaling analysis for inertia tank based on the cold state of deep pool-type nuclear heating reactor
|
Wang, Gongqing
|
|
|
151 |
C |
p.
|
artikel
|
| 80 |
Sensitivity and uncertainty analyses of a high temperature gas-cooled reactor by using a 44-group covariance library
|
Hartanto, Donny
|
|
|
151 |
C |
p.
|
artikel
|
| 81 |
Sensitivity of the neutron multiplication factor to gadolinium isotopes’ nuclear data for light water reactor fuel assemblies in the peak reactivity burnup range
|
Chiba, Go
|
|
|
151 |
C |
p.
|
artikel
|
| 82 |
Simulations for worth determination of CPSARs in VVER-1000 reactor using EXCEL and TRIHEX-FA code system
|
Thilagam, L.
|
|
|
151 |
C |
p.
|
artikel
|
| 83 |
Study on algorithms for solving depletion sparse matrix based on DESCAR module
|
Guo, Fengchen
|
|
|
151 |
C |
p.
|
artikel
|
| 84 |
Study on evaluation method for nuclear emergency rescue measures at containment vessel
|
Ruan, Fang
|
|
|
151 |
C |
p.
|
artikel
|
| 85 |
Study on evidence-based LPSA method in nuclear power plant under abnormal operating conditions
|
Lu, Hongxing
|
|
|
151 |
C |
p.
|
artikel
|
| 86 |
Thermal-hydraulic efficiency of a modular reactor power plant by using the second law of thermodynamic
|
Norouzi, Nima
|
|
|
151 |
C |
p.
|
artikel
|
| 87 |
Thermochemical changes on swelling pressure of compacted bentonite
|
Kim, Minseop
|
|
|
151 |
C |
p.
|
artikel
|
| 88 |
Third order adjoint sensitivity analysis of reaction rate responses in a multiplying nuclear system with source
|
Cacuci, Dan Gabriel
|
|
|
151 |
C |
p.
|
artikel
|
| 89 |
Three-dimensional thermal–hydraulic coupled analysis in the nuclear waste repository
|
Zhou, Xiangyun
|
|
|
151 |
C |
p.
|
artikel
|
| 90 |
Two decades on human reliability analysis: A bibliometric analysis and literature review
|
Hou, Lin-Xiu
|
|
|
151 |
C |
p.
|
artikel
|
| 91 |
Virtual element methods for the spatial discretisation of the multigroup neutron diffusion equation on polygonal meshes with applications to nuclear reactor physics
|
Ferguson, J.A.
|
|
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151 |
C |
p.
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artikel
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