| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Adsorption of uranium (VI) by amidoxime modified multiwalled carbon nanotubes
|
Wu, Jinling
|
|
|
106 |
C |
p. 79-86
|
artikel
|
| 2 |
Adsorptive removal of radioactive isotopes of cobalt and zinc from water and radioactive wastewater using TiO2/Ag2O nanoadsorbents
|
Mahmoud, Mohamed E.
|
|
|
106 |
C |
p. 51-63
|
artikel
|
| 3 |
A full-digital multidimensional redundancy control system for high intensity D-T fusion neutron generator
|
Zhang, Yong
|
|
|
106 |
C |
p. 367-371
|
artikel
|
| 4 |
Americium and Plutonium Purification by Extraction (the AMPPEX process): Development of a new method to separate 241Am from aged plutonium dioxide for use in space power systems
|
Brown, Jamie
|
|
|
106 |
C |
p. 396-416
|
artikel
|
| 5 |
Analysis of Design Extension Conditions in a heavy water research reactor
|
Khaki Arani, Mehdi
|
|
|
106 |
C |
p. 44-50
|
artikel
|
| 6 |
An experimental investigation on the drying of thorium oxalate in a batch spouted bed dryer
|
Beigi, Sadegh
|
|
|
106 |
C |
p. 465-473
|
artikel
|
| 7 |
An investigation on the physical and chemical behaviors of fuel debris during severe accident progression
|
Song, JinHo
|
|
|
106 |
C |
p. 345-356
|
artikel
|
| 8 |
A non-equilibrium control oriented model for the pressurizer dynamics
|
Pini, Alessandro
|
|
|
106 |
C |
p. 102-119
|
artikel
|
| 9 |
An optimized epithermal BNCT beam design for research reactors
|
Hassanein, A.M.
|
|
|
106 |
C |
p. 455-464
|
artikel
|
| 10 |
Axial dispersion and pressure drop for single-phase flow in annular pulsed disc and doughnut columns: A CFD study
|
Sarkar, Sourav
|
|
|
106 |
C |
p. 335-344
|
artikel
|
| 11 |
Control rod drop-time reduction in typical swimming pool research reactors
|
Salmanpour Paean Afrakati, M.R.
|
|
|
106 |
C |
p. 146-152
|
artikel
|
| 12 |
Coupling of neutronics and thermal-hydraulics codes for the simulation of reactivity insertion accident for LFR
|
Yang, Dongmei
|
|
|
106 |
C |
p. 20-26
|
artikel
|
| 13 |
Decisions on nuclear decommissioning strategies: Historical review
|
Suh, Young A
|
|
|
106 |
C |
p. 34-43
|
artikel
|
| 14 |
Development of a research reactor protocol for neutron multiplication measurements
|
Arthur, Jennifer
|
|
|
106 |
C |
p. 120-139
|
artikel
|
| 15 |
Developments of analyses on grid-to-rod fretting problems in pressurized water reactors
|
Hu, Zupan
|
|
|
106 |
C |
p. 293-299
|
artikel
|
| 16 |
Editorial Board
|
|
|
|
106 |
C |
p. ii
|
artikel
|
| 17 |
Experimental and numerical analysis of transient natural convection of water in a high aspect ratio narrow vertical annulus
|
Husain, Shahid
|
|
|
106 |
C |
p. 1-10
|
artikel
|
| 18 |
Experimental characterization of a random packing with high specific surface area in a small diameter cryogenic distillation column
|
Avili, Mohammad Ghomi
|
|
|
106 |
C |
p. 417-424
|
artikel
|
| 19 |
Experimental study on molten metal spreading and deposition behaviors on wet surface
|
Ogura, Takahito
|
|
|
106 |
C |
p. 72-78
|
artikel
|
| 20 |
FEA-based metal sphere signal map for mass estimation of simulated loose part in reactor coolant system
|
Moon, Seong-In
|
|
|
106 |
C |
p. 357-366
|
artikel
|
| 21 |
Flexible X/Gamma ray shielding composite material of EPDM rubber with bismuth trioxide: Mechanical, thermal investigations and attenuation tests
|
Güngör, A.
|
|
|
106 |
C |
p. 262-269
|
artikel
|
| 22 |
Fusible alloys: A potential candidate for gamma rays shield design
|
Singh, Jaspreet
|
|
|
106 |
C |
p. 387-395
|
artikel
|
| 23 |
Improved resource utilization by advanced burner reactors with breed-and-burn blankets
|
Zhang, Guanheng
|
|
|
106 |
C |
p. 440-454
|
artikel
|
| 24 |
Initial verification of AZNHEX hexagonal-z neutron diffusion code with MCNP6 for two different study cases
|
Galicia-Aragón, Juan
|
|
|
106 |
C |
p. 284-292
|
artikel
|
| 25 |
Mass transfer experiments on the natural convection heat transfer of the oxide pool in a three-layer configuration
|
Kim, Su-Hyeon
|
|
|
106 |
C |
p. 11-19
|
artikel
|
| 26 |
Measurement on effective thermal diffusivity and conductivity of pebble bed under vacuum condition in High Temperature Gas-cooled Reactor
|
Wu, Yongyong
|
|
|
106 |
C |
p. 195-203
|
artikel
|
| 27 |
Neutron importance behavior in a VVER-1000 core during reactor operating cycle
|
Jafarikia, S.
|
|
|
106 |
C |
p. 64-71
|
artikel
|
| 28 |
Nuclear data adjustment exercise combining information from shielding, critical and kinetics benchmark experiments ASPIS-Iron 88, Popsy and SNEAK-7A/7B
|
Kodeli, Ivan A.
|
|
|
106 |
C |
p. 215-230
|
artikel
|
| 29 |
Optimal placement of fixed in-core detectors for Tehran Research Reactor using information theory
|
Terman, Mohammad Sadegh
|
|
|
106 |
C |
p. 300-315
|
artikel
|
| 30 |
Pebble bed nuclear reactor structure study: A comparison of the experimental and calculated void fraction distribution
|
Al Falahi, Fadha
|
|
|
106 |
C |
p. 153-161
|
artikel
|
| 31 |
Preparation, shielding properties and mechanism of a novel neutron shielding material made from natural Szaibelyite resource
|
Dong, Mengge
|
|
|
106 |
C |
p. 140-145
|
artikel
|
| 32 |
Research and development activities for accelerator-driven system in JAEA
|
Sugawara, Takanori
|
|
|
106 |
C |
p. 27-33
|
artikel
|
| 33 |
Safety analysis of Super-Critical Water Reactors–A review
|
Rowinski, Marcin Karol
|
|
|
106 |
C |
p. 87-101
|
artikel
|
| 34 |
SiC cladding thermal conductivity requirements for normal operation and LOCA conditions
|
Cozzo, C.
|
|
|
106 |
C |
p. 278-283
|
artikel
|
| 35 |
Stability analysis of the Generation-IV nuclear reactors by means of the root locus criterion
|
Cervi, E.
|
|
|
106 |
C |
p. 316-334
|
artikel
|
| 36 |
State change modal method for numerical simulation of dynamic processes in a nuclear reactor
|
Avvakumov, Alexander V.
|
|
|
106 |
C |
p. 240-261
|
artikel
|
| 37 |
Stress-testing the ALFRED design - Part III: Safety margins evaluation
|
Lodi, F.
|
|
|
106 |
C |
p. 433-439
|
artikel
|
| 38 |
Stress-testing the ALFRED design – Part I: Impact of nuclear data uncertainties on Design Extension Conditions transients
|
Grasso, G.
|
|
|
106 |
C |
p. 372-386
|
artikel
|
| 39 |
The seismic analysis of the core structure in a pool-type material test reactor using 3-D finite difference method
|
Hedayat, Afshin
|
|
|
106 |
C |
p. 162-180
|
artikel
|
| 40 |
The U-232 production in thorium cycle
|
Wojciechowski, Andrzej
|
|
|
106 |
C |
p. 204-214
|
artikel
|
| 41 |
Transient safety analysis for simplified accelerator driven system with gas-lift pump
|
Zuo, Juanli
|
|
|
106 |
C |
p. 181-194
|
artikel
|
| 42 |
Using MCNP for success criteria evaluation of reactor trip function in probabilistic modeling of ATWS upon LOOP
|
Kamyab, Sh.
|
|
|
106 |
C |
p. 270-277
|
artikel
|
| 43 |
Validation of RELAP5 MOD3.3 code for entrainment phenomenon against FATE test facility
|
Hu, Xiao
|
|
|
106 |
C |
p. 425-432
|
artikel
|
| 44 |
Vibration of core subassemblies due to large sodium–water reaction in the steam generator of a Liquid Metal Fast Breeder Reactor
|
Sumathi, V.
|
|
|
106 |
C |
p. 231-239
|
artikel
|
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