| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A conceptual methodology for site exclusion boundary and site large early release frequency for multi-unit nuclear power plants site
|
Prasad, Mahendra
|
|
|
137 |
C |
p.
|
artikel
|
| 2 |
Adaptive backstepping controller with extended state observer for load following of nuclear power plant
|
Hui, Jiuwu
|
|
|
137 |
C |
p.
|
artikel
|
| 3 |
Applicability of polymer and composite inner linings in containers for borehole disposal of sealed radioactive sources − A simulation-based study of radiation effects
|
Vujović, Milan
|
|
|
137 |
C |
p.
|
artikel
|
| 4 |
Application of the coupled code ATHLET-ANSYS CFX for the simulation of the flow mixing inside the ROCOM test facility
|
Papukchiev, Angel
|
|
|
137 |
C |
p.
|
artikel
|
| 5 |
A proposed improvement for the design of safety injection system in VVER-1000/V446 reactor
|
Ramezani, Ahmad
|
|
|
137 |
C |
p.
|
artikel
|
| 6 |
CFD study on crossflow and heat transfer characteristics of single phase flow in rod bundle with spacer grid under rolling conditions
|
Wang, Sipeng
|
|
|
137 |
C |
p.
|
artikel
|
| 7 |
Characterization of the radiation shielding properties of fired lead sample for X-ray shielding applications
|
Umeh, Chibuike Dominic
|
|
|
137 |
C |
p.
|
artikel
|
| 8 |
Comparative study of the supercritical carbon-dioxide recompression Brayton cycle with different control strategies
|
Ding, Hao
|
|
|
137 |
C |
p.
|
artikel
|
| 9 |
Computational fluid dynamics analysis of buoyancy-aided turbulent mixed convection inside a heated vertical rectangular duct
|
Kim, Sin-Yeob
|
|
|
137 |
C |
p.
|
artikel
|
| 10 |
Consistency and shielding efficiency of cement-bitumen composite for use as gamma-radiation shielding material
|
Saleh, Hosam M.
|
|
|
137 |
C |
p.
|
artikel
|
| 11 |
Dense and environment friendly bismuth barium telluroborate glasses for nuclear protection applications
|
Al-Buriahi, M.S.
|
|
|
137 |
C |
p.
|
artikel
|
| 12 |
Development of a membrane reactor with a closed-end silica membrane for nuclear-heated hydrogen production
|
Myagmarjav, Odtsetseg
|
|
|
137 |
C |
p.
|
artikel
|
| 13 |
Development, verification, and validation of the parallel transport code AZTRAN
|
Duran-Gonzalez, Julian
|
|
|
137 |
C |
p.
|
artikel
|
| 14 |
Digital inspection approach of overlapped peaks due to high counting rates in neutron spectroscopy
|
El_Tokhy, Mohamed S.
|
|
|
137 |
C |
p.
|
artikel
|
| 15 |
Dissolved ozone coupled permanganate based process for chemical decontamination of stainless steel surfaces
|
Maroo, Sonal
|
|
|
137 |
C |
p.
|
artikel
|
| 16 |
Early-stage corrosion behavior of Al-based Gd2O3–W shielding composites in a simulated spent fuel wet storage environment
|
Cong, Shuo
|
|
|
137 |
C |
p.
|
artikel
|
| 17 |
Editorial Board
|
|
|
|
137 |
C |
p.
|
artikel
|
| 18 |
Effects of helical obstacle on heat transfer and flow in a tube
|
Fagr, Mohsen H.
|
|
|
137 |
C |
p.
|
artikel
|
| 19 |
Effects of liquid film waviness, suction, and fog formation on condensation in the presence of noncondensable gases
|
Lu, Junhui
|
|
|
137 |
C |
p.
|
artikel
|
| 20 |
Fuel performance analysis of reduced moderated boiling water reactor for transuranic waste incineration
|
Sukjai, Yanin
|
|
|
137 |
C |
p.
|
artikel
|
| 21 |
Gamma radiation attenuation characteristics of polyimide composite with WO2
|
Cherkashina, N.I.
|
|
|
137 |
C |
p.
|
artikel
|
| 22 |
Impact of alkali activated mortar incorporating different heavy metals on immobilization proficiency using gamma rays attenuation
|
Khater, H.M.
|
|
|
137 |
C |
p.
|
artikel
|
| 23 |
Implementation of Gray Wolf Optimization algorithm to recycled gas centrifuge cascades
|
Dadashzadeh, S.
|
|
|
137 |
C |
p.
|
artikel
|
| 24 |
Investigation of capillary size on the separation factor of gaseous separation membrane with DSMC method
|
Masir, M. Abedi
|
|
|
137 |
C |
p.
|
artikel
|
| 25 |
Investigation on shielding properties of lead based alloys
|
Sathish, K.V.
|
|
|
137 |
C |
p.
|
artikel
|
| 26 |
Long-term initiation time for stress -corrosion cracking of alloy 600 with implications in stainless steel: Review and analysis for nuclear application
|
Ahn, Tae M.
|
|
|
137 |
C |
p.
|
artikel
|
| 27 |
Marvin: A parallel three-dimensional transport code based on the discrete ordinates method for reactor shielding calculations
|
Zhang, Guangchun
|
|
|
137 |
C |
p.
|
artikel
|
| 28 |
Microstructure transformation of Mo–3Nb single crystal used for space thermionic reactor during welding
|
Ma, Yan
|
|
|
137 |
C |
p.
|
artikel
|
| 29 |
Modeling of gas jet flow into a liquid bath using the inhomogeneous poly-dispersed method
|
Qu, Xiaohang
|
|
|
137 |
C |
p.
|
artikel
|
| 30 |
Performance and economic assessment of enriched gadolinia burnable absorbers
|
Bolukbasi, M.J.
|
|
|
137 |
C |
p.
|
artikel
|
| 31 |
Prompt gamma-rays in three H-rich moderators exposed to neutrons
|
Garcia-Reyna, Mayra Guadalupe
|
|
|
137 |
C |
p.
|
artikel
|
| 32 |
Radiation shielding properties of concrete containing magnetite
|
Gunoglu, Kadir
|
|
|
137 |
C |
p.
|
artikel
|
| 33 |
Radiation shielding properties of selected alloys using EPICS2017 data library
|
Almuqrin, Aljawhara H.
|
|
|
137 |
C |
p.
|
artikel
|
| 34 |
Radiological characterisation in view of nuclear reactor decommissioning: On-site benchmarking exercise of a biological shield
|
Herranz, Margarita
|
|
|
137 |
C |
p.
|
artikel
|
| 35 |
Rankine-vortex model based assessment of CFD methods for simulating the effect of gas entrainment observed in the hot-pool of sodium coold fast breeder reactors
|
Bhatia, H.
|
|
|
137 |
C |
p.
|
artikel
|
| 36 |
Recommendations for the selection of in situ measurement techniques for radiological characterization in nuclear/radiological installations under decommissioning and dismantling processes
|
Amgarou, Khalil
|
|
|
137 |
C |
p.
|
artikel
|
| 37 |
Solubility, structure transition and chemical durability of Th-doped Nd2Zr2O7 pyrochlore
|
Wang, Lielin
|
|
|
137 |
C |
p.
|
artikel
|
| 38 |
Temperature effect on the thermal and hydraulic conductivity of Korean bentonite buffer material
|
Park, Seunghun
|
|
|
137 |
C |
p.
|
artikel
|
| 39 |
The important role and performance of engineered barriers in a UK geological disposal facility for higher activity radioactive waste
|
Marsh, Ashley I.
|
|
|
137 |
C |
p.
|
artikel
|
| 40 |
Thermal analyses of TN-24P dry storage cask with heterogeneous fuel assembly modeling
|
Yun, Hyungju
|
|
|
137 |
C |
p.
|
artikel
|
| 41 |
Time-dependent Green's function generation with Monte Carlo for transient analysis of source-driven systems
|
R. Maleki, Bahram
|
|
|
137 |
C |
p.
|
artikel
|
| 42 |
Utilizing neutronics modelling to predict changing Pu ratios in UO2 in the presence of Th
|
Evitts, L.J.
|
|
|
137 |
C |
p.
|
artikel
|
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