| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
An accessible statistical regression approach for the estimation of spent nuclear fuel compositions and decay heats to support the development of nuclear fuel management strategies
|
Holdsworth, Alistair F.
|
|
|
141 |
C |
p.
|
artikel
|
| 2 |
Analysis of venting strategies and hydrogen concentration evolution during a station blackout in a BWR-6 containment using GOTHIC 8.3
|
Díez Álvarez-Buylla, Pino
|
|
|
141 |
C |
p.
|
artikel
|
| 3 |
An analytical approach to organ equivalent dose estimation based on material composition photon attenuation coefficient
|
Miyombo, Miyombo Ernest
|
|
|
141 |
C |
p.
|
artikel
|
| 4 |
Atoms for electricity generation in Africa: Analysis of factors affecting the continent's readiness
|
Ansah, Michael Nii Sanka
|
|
|
141 |
C |
p.
|
artikel
|
| 5 |
Behavior of Emergency Core Cooling System (ECCS) during the early stage of Loss of Coolant Accident (LOCA) for APR 1400 with Flownex software
|
Zubair, Muhammad
|
|
|
141 |
C |
p.
|
artikel
|
| 6 |
Boiling heat transfer experiments under power transients for LWRs: A review study
|
He, Mingfu
|
|
|
141 |
C |
p.
|
artikel
|
| 7 |
CFD simulation and flow-induced vibration evaluation of PWR steam generator U tubes
|
Guangming, Xiong
|
|
|
141 |
C |
p.
|
artikel
|
| 8 |
Compact nuclear-driven semiconductor reactor/laser system
|
Wisniewski, Denis Alexander
|
|
|
141 |
C |
p.
|
artikel
|
| 9 |
Comparative analysis of core life-time for the NIRR-1 HEU and LEU cores
|
Simon, J.
|
|
|
141 |
C |
p.
|
artikel
|
| 10 |
Core design and fuel behaviour of a small modular pressurised water reactor using (Th,U)O 2 fuel for commercial marine propulsion
|
Peakman, Aiden
|
|
|
141 |
C |
p.
|
artikel
|
| 11 |
Development and validation of a two-fluid three-field model for the vertical upward flow
|
Fan, Jie
|
|
|
141 |
C |
p.
|
artikel
|
| 12 |
Editorial Board
|
|
|
|
141 |
C |
p.
|
artikel
|
| 13 |
Effect of Fe2O3 doping on structural, FTIR and radiation shielding characteristics of aluminium-lead-borate glasses
|
Albarzan, Badriah
|
|
|
141 |
C |
p.
|
artikel
|
| 14 |
Effect of HAF carbon black on curing, mechanical, thermal and neutron shielding properties of natural rubber - Low-density polyethylene composites
|
Sajith, T.A.
|
|
|
141 |
C |
p.
|
artikel
|
| 15 |
Evaluation of the shielding properties of a new increased capacity storage cask for RBMK-1500 used fuel
|
Smaizys, Arturas
|
|
|
141 |
C |
p.
|
artikel
|
| 16 |
Experimental investigation on dispersed phase holdup in an L-shape pulsed packed extraction column
|
Khooshechin, Sajad
|
|
|
141 |
C |
p.
|
artikel
|
| 17 |
Experimental modeling and uncertainty analysis of dispersed phase holdup at flooding in a pulsed disc-doughnut column, case study: Response surface methodology and Monte-Carlo simulation
|
Shakib, Benyamin
|
|
|
141 |
C |
p.
|
artikel
|
| 18 |
Experimental study on fine particle deposition in supercritical water natural circulation
|
Tao, Zhou
|
|
|
141 |
C |
p.
|
artikel
|
| 19 |
Fabrication of novel neutron shielding materials: Polypropylene composites containing colemanite, tincal and ulexite
|
Bilici, İbrahim
|
|
|
141 |
C |
p.
|
artikel
|
| 20 |
Gamma radiation attenuation characteristics of composites based on polyimide track membranes filled with nanodispersed Pb
|
Cherkashina, N.I.
|
|
|
141 |
C |
p.
|
artikel
|
| 21 |
Irradiation in BCC materials: Defect-induced changes of the effective dislocation mobility and their relation with the dose-dependent fracture response
|
Singh, Kulbir
|
|
|
141 |
C |
p.
|
artikel
|
| 22 |
Load-following control of a nuclear reactor using optimized FOPID controller based on the two-point fractional neutron kinetics model considering reactivity feedback effects
|
Rafiei, M.
|
|
|
141 |
C |
p.
|
artikel
|
| 23 |
Method for measuring the saturated permeability coefficient of compacted bentonite at temperatures exceeding 100 °C
|
Li, Hui
|
|
|
141 |
C |
p.
|
artikel
|
| 24 |
Nuclear radiation shielding characteristics and physical, optical, mechanical, and thermal properties of lithium-borotellurite glass doped with Rb2O
|
Kurtulus, Recep
|
|
|
141 |
C |
p.
|
artikel
|
| 25 |
Nuclear shielding properties and buildup factors of Cr-based ferroalloys
|
Alzahrani, Jamila S.
|
|
|
141 |
C |
p.
|
artikel
|
| 26 |
Numerical investigation of flow and heat transfer characteristics in plate-type fuel channels of IAEA MTR based on OpenFOAM
|
Liu, Kai
|
|
|
141 |
C |
p.
|
artikel
|
| 27 |
Radiation-thermal stability of hydrazine nitrate in nitric acid solutions
|
Belova, Elena
|
|
|
141 |
C |
p.
|
artikel
|
| 28 |
Solidification of radioactive wastes by cement-based materials
|
Li, Junfeng
|
|
|
141 |
C |
p.
|
artikel
|
| 29 |
Source term investigation for a prolonged loss of cooling accident, for a typical CANDU spent fuel pool, during the refurbishment process
|
Constantin, Marin
|
|
|
141 |
C |
p.
|
artikel
|
| 30 |
Study of the spent resins confinement, as radioactive waste, by cementation in the presence of Moroccan natural red clay
|
Sadiq, Asmae
|
|
|
141 |
C |
p.
|
artikel
|
| 31 |
Study on NC in primary loop and reverse flow in SG during SBO combining with SBLOCA
|
Li, Mingrui
|
|
|
141 |
C |
p.
|
artikel
|
| 32 |
Thermal-hydraulic constitutive equations implemented in the system analysis code AMAGI for nuclear power reactor
|
Hibiki, Takashi
|
|
|
141 |
C |
p.
|
artikel
|
| 33 |
Utilization of Military Grade Plutonium in Generation-IV Gas Cooled Fast Reactor
|
Ibrahim, Amr
|
|
|
141 |
C |
p.
|
artikel
|
| 34 |
Vortex shedding induced vibration of thin strip in confined rectangular channel
|
Zhang, Botao
|
|
|
141 |
C |
p.
|
artikel
|
| 35 |
Young Chinese people's perceptions of nuclear power: Connection with enthusiasm for information, perceptions of nuclear reactor technology and NIMBY
|
Wu, Hsingtzu
|
|
|
141 |
C |
p.
|
artikel
|
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