| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A Haar wavelet method for angularly discretising the Boltzmann transport equation
|
Adigun, Babatunde J.
|
|
|
108 |
C |
p. 295-309
|
artikel
|
| 2 |
A modified predictor-corrector quasi-static method in NECP-X for reactor transient analysis based on the 2D/1D transport method
|
Wang, Bo
|
|
|
108 |
C |
p. 122-135
|
artikel
|
| 3 |
Analysis of the releases produced by CANDU type irradiated fuel bundles accidentally remained in the air
|
Constantin, Marin
|
|
|
108 |
C |
p. 351-357
|
artikel
|
| 4 |
A new security strategy for small medium sized reactor (SMR) plants
|
Lee, Manseok
|
|
|
108 |
C |
p. 66-70
|
artikel
|
| 5 |
A novel multi-objective optimization method, imperialist competitive algorithm, for fuel loading pattern of nuclear reactors
|
Akbari, R.
|
|
|
108 |
C |
p. 391-397
|
artikel
|
| 6 |
Application of an adjoint technique to one–speed X , Y –geometry source–detector transport problems in the discrete ordinates formulation using a spectral nodal method
|
Curbelo, Jesús P.
|
|
|
108 |
C |
p. 445-453
|
artikel
|
| 7 |
Assessment of an integral small modular reactor during rod ejection accident by using DRAGON/PARCS codes
|
Akbari-Jeyhouni, Reza
|
|
|
108 |
C |
p. 136-143
|
artikel
|
| 8 |
Atmospheric dispersion assessment of radioactive materials during severe accident conditions for Bushehr nuclear power plant using HYSPLIT code
|
Pirouzmand, Ahmad
|
|
|
108 |
C |
p. 169-178
|
artikel
|
| 9 |
Cesium extraction from simulated high-level vitrified wastes
|
Xu, Zhanglian
|
|
|
108 |
C |
p. 34-42
|
artikel
|
| 10 |
CFD simulation of heated tight-lattice rod bundles for an IAEA benchmark
|
Podila, K.
|
|
|
108 |
C |
p. 222-232
|
artikel
|
| 11 |
Combined cycle schemes coupled with a Very High Temperature gas-cooled reactor
|
Xinhe, Qu
|
|
|
108 |
C |
p. 1-10
|
artikel
|
| 12 |
Conceptual design of a bayonet tube steam generator with heat transfer enhancement using a helical coiled downcomer
|
Bersano, Andrea
|
|
|
108 |
C |
p. 243-252
|
artikel
|
| 13 |
Core design and performance of the FASt TEst reactor (FASTER)
|
Heidet, F.
|
|
|
108 |
C |
p. 480-488
|
artikel
|
| 14 |
Design concepts of small CANDLE reactor with melt-refining process
|
Hoang, Van Khanh
|
|
|
108 |
C |
p. 233-242
|
artikel
|
| 15 |
Development of cone-wedge-ring-expansion test to evaluate the tensile HOOP properties of nuclear fuel cladding
|
Jiang, Hao
|
|
|
108 |
C |
p. 372-380
|
artikel
|
| 16 |
Development of high thermal conductivity UO2–Th heterogeneous fuel
|
Ševeček, Martin
|
|
|
108 |
C |
p. 489-496
|
artikel
|
| 17 |
Development of NPP digital I&C system closed-loop online test system based on signal transmission array
|
Yang, Minghan
|
|
|
108 |
C |
p. 270-280
|
artikel
|
| 18 |
Editorial Board
|
|
|
|
108 |
C |
p. ii
|
artikel
|
| 19 |
Effect of higher harmonics in the area-ratio pulsed neutron source technique
|
Yamamoto, Toshihiro
|
|
|
108 |
C |
p. 286-294
|
artikel
|
| 20 |
Effect of void fraction covariance on two-fluid model based code calculation in pipe flow
|
Ozaki, Tetsuhiro
|
|
|
108 |
C |
p. 319-333
|
artikel
|
| 21 |
Evolution of grid-to-rod fretting of nuclear fuel rods during burnup
|
Dyk, Š.
|
|
|
108 |
C |
p. 160-168
|
artikel
|
| 22 |
Experimental study of the characteristics of an upward two-phase slug flow in a vertical pipe
|
Saidj, Faiza
|
|
|
108 |
C |
p. 428-437
|
artikel
|
| 23 |
Experimental validation of the neutronic parameters in the Jordan subcritical assembly
|
Jarrah, Ibrahim
|
|
|
108 |
C |
p. 71-80
|
artikel
|
| 24 |
FASt TEst Reactor (FASTER) design overview
|
Heidet, F.
|
|
|
108 |
C |
p. 465-473
|
artikel
|
| 25 |
Flow patterns and transition criteria in boiling water-cooled packed bed reactors
|
Xu, Guangzhan
|
|
|
108 |
C |
p. 214-221
|
artikel
|
| 26 |
Fuel pebble optimization for the thorium-fueled Pebble Bed Fluoride salt-cooled high-temperature reactor (PB-TFHR)
|
Fang, Y.H.
|
|
|
108 |
C |
p. 179-187
|
artikel
|
| 27 |
Improvement of the condensation heat transfer model of the MARS-KS1.3 code using a modified diffusion layer model
|
Lee, Jun-Yeob
|
|
|
108 |
C |
p. 260-269
|
artikel
|
| 28 |
Investigation of single bubble rising velocity in LBE by transparent liquids similarity experiments
|
Zhang, Chaodong
|
|
|
108 |
C |
p. 204-213
|
artikel
|
| 29 |
Investigation of VVER-1000 rod ejection accident according to the Phenomenon Identification and Ranking Tables for PWR
|
Miglierini, Bruno
|
|
|
108 |
C |
p. 438-444
|
artikel
|
| 30 |
Investing in a permanent and sustainable nuclear waste disposal solution
|
Yano, Kayla H.
|
|
|
108 |
C |
p. 474-479
|
artikel
|
| 31 |
Measurement of tungsten reactivity worth on VENUS-II light water reactor and validation of evaluated nuclear data
|
Jiang, Wei
|
|
|
108 |
C |
p. 81-88
|
artikel
|
| 32 |
Melt jet-breakup and fragmentation phenomena in nuclear reactors: A review of experimental works and solidification effects
|
Iwasawa, Yuzuru
|
|
|
108 |
C |
p. 188-203
|
artikel
|
| 33 |
Mining data in a dynamic PRA framework
|
Mandelli, D.
|
|
|
108 |
C |
p. 99-110
|
artikel
|
| 34 |
New turbulence modeling for simulation of Direct Contact Condensation in two-phase pressurized thermal shock
|
Ghafari, M.
|
|
|
108 |
C |
p. 358-371
|
artikel
|
| 35 |
Optimal design of supercritical CO2 power cycle for next generation nuclear power conversion systems
|
Guo, Zhangpeng
|
|
|
108 |
C |
p. 111-121
|
artikel
|
| 36 |
Optimization of dry cask loadings for used nuclear fuel management strategies
|
Spencer, Kristina Yancey
|
|
|
108 |
C |
p. 11-25
|
artikel
|
| 37 |
Optimization of Th-U fuel breeding based on a single-fluid double-zone thorium molten salt reactor
|
Li, G.C.
|
|
|
108 |
C |
p. 144-151
|
artikel
|
| 38 |
Parametric study of thermal molten salt reactor neutronics criticality behavior
|
Wei, Hongyang
|
|
|
108 |
C |
p. 409-418
|
artikel
|
| 39 |
Reactivity and flux characterization of the Jordan subcritical assembly
|
Radaideh, Majdi I.
|
|
|
108 |
C |
p. 43-53
|
artikel
|
| 40 |
Research on intelligent fault diagnosis method for nuclear power plant based on correlation analysis and deep belief network
|
Peng, Bin-Sen
|
|
|
108 |
C |
p. 419-427
|
artikel
|
| 41 |
Results of simulant effect on large corium pool behavior based on COPRA facility
|
Zhou, Y.K.
|
|
|
108 |
C |
p. 398-408
|
artikel
|
| 42 |
Retraction notice to “Subchannel Analysis of TiO2 Nanofluid as the Coolant in VVER-1000 Reactor” Progress in Nuclear Energy 73, (2014), 140-152
|
Zarifi, Ehsan
|
|
|
108 |
C |
p. 518
|
artikel
|
| 43 |
Retraction notice to “Superior techniques for disposal of highly radioactive waste (HLW)” [Progress in Nuclear Energy 59, (2012), 75-85]
|
Pusch, Roland
|
|
|
108 |
C |
p. 517
|
artikel
|
| 44 |
Review of the environmental oversight framework in Kenya, in light of a nuclear power programme
|
Musyoka, Diana
|
|
|
108 |
C |
p. 89-98
|
artikel
|
| 45 |
Safety analysis of the FASt TEst reactor (FASTER) preconceptual design
|
Sumner, Tyler
|
|
|
108 |
C |
p. 454-464
|
artikel
|
| 46 |
Simplified two-group two-fluid model for three-dimensional two-phase flow Computational Fluid Dynamics for vertical upward flow
|
Hibiki, Takashi
|
|
|
108 |
C |
p. 503-516
|
artikel
|
| 47 |
Simulation of radionuclide diffusion in a dry storage of spent fuel under accident condition
|
Chen, Liwei
|
|
|
108 |
C |
p. 152-159
|
artikel
|
| 48 |
Small modular reactors: Methodology of economic assessment focused on incremental construction and gradual shutdown options
|
Liman, Jakub
|
|
|
108 |
C |
p. 253-259
|
artikel
|
| 49 |
The cost-benefit analysis of the optimal Type-I (α) and Type-II (β) error values for nuclear material accounting and safeguards
|
Woo, Seung Min
|
|
|
108 |
C |
p. 281-285
|
artikel
|
| 50 |
The development and validation of the inter-wrapper flow model in sodium-cooled fast reactors
|
Yue, Nina
|
|
|
108 |
C |
p. 54-65
|
artikel
|
| 51 |
Thermal-hydraulic noise analysis of a VVER-1000 reactor with nanofluid as coolant
|
Nourollahi, Reza
|
|
|
108 |
C |
p. 334-350
|
artikel
|
| 52 |
The strategic value of human factors engineering in control room modernization
|
Hugo, Jacques V.
|
|
|
108 |
C |
p. 381-390
|
artikel
|
| 53 |
Treatment of spent nuclear fuel debris contaminated water in the Taiwan Research Reactor spent fuel pool
|
Huang, Chun-Ping
|
|
|
108 |
C |
p. 26-33
|
artikel
|
| 54 |
Vitrification processes of simulated cesium sorbing zeolite waste
|
Kimura, Ryou
|
|
|
108 |
C |
p. 497-502
|
artikel
|
| 55 |
Whole-core forward-adjoint neutron transport solutions with coupled 2-D MOC and 1-D SN and kinetics parameter calculation
|
Wu, Qu
|
|
|
108 |
C |
p. 310-318
|
artikel
|
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