| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Analysis on the behavior of dispersed plate-type fuel based on fluid-solid coupling method
|
Li, Chenxi
|
|
|
126 |
C |
p.
|
artikel
|
| 2 |
An improved A* algorithm for searching the minimum dose path in nuclear facilities
|
Chen, Chen
|
|
|
126 |
C |
p.
|
artikel
|
| 3 |
Application of experimental measurements, Monte Carlo simulation and theoretical calculation to estimate the gamma ray shielding capacity of various natural rocks
|
Bantan, Rashad A R
|
|
|
126 |
C |
p.
|
artikel
|
| 4 |
Continuous synthesis of tributyl phosphate in microreactor
|
Sen, Nirvik
|
|
|
126 |
C |
p.
|
artikel
|
| 5 |
3D fluid-solid coupling simulation for plate-type nuclear fuel assemblies under the irradiation condition
|
Liao, Haoyu
|
|
|
126 |
C |
p.
|
artikel
|
| 6 |
Dynamic analysis for a 2 MW liquid-fueled molten salt reactor
|
Cui, Y.
|
|
|
126 |
C |
p.
|
artikel
|
| 7 |
Editorial Board
|
|
|
|
126 |
C |
p.
|
artikel
|
| 8 |
Effects of mixture parameters variation on the performance of corrugated plate dryer
|
Mao, Feng
|
|
|
126 |
C |
p.
|
artikel
|
| 9 |
Evaluation of gamma ray shielding characteristics of CaF2–BaO –P2O5 glass system using Phy-X / PSD computer program
|
Al-Hadeethi, Y.
|
|
|
126 |
C |
p.
|
artikel
|
| 10 |
Experimental study on the scrubbing efficiency of aerosols contained in horizontal and vertically downward submerged gas jet
|
Diao, Han
|
|
|
126 |
C |
p.
|
artikel
|
| 11 |
Fission matrix homogenization and iterative convergence in RAPID
|
He, Donghao
|
|
|
126 |
C |
p.
|
artikel
|
| 12 |
Influence of surface area of counter electrodes in electro-denitration process
|
Mishra, Satyabrata
|
|
|
126 |
C |
p.
|
artikel
|
| 13 |
Innovative passive management of the Station Black-Out accident for VVER1000/V446 NPP and development of its emergency operating procedures
|
Hosseini, M.M.
|
|
|
126 |
C |
p.
|
artikel
|
| 14 |
Investigation of the effects of the impeller blades and vane blades on the CAP1400 nuclear coolant pump's performances with a united optimal design technology
|
Lu, Yeming
|
|
|
126 |
C |
p.
|
artikel
|
| 15 |
Investigations on thermal and radiation shielding properties of the poly(hydroxyethyl methacrylate-co-styrene)/tungsten(VI) oxide composites
|
Körpınar, Berna
|
|
|
126 |
C |
p.
|
artikel
|
| 16 |
Methodology for neutronic uncertainty propagation and application to a UAM-LWR benchmark
|
Mesado, C.
|
|
|
126 |
C |
p.
|
artikel
|
| 17 |
Multi-module program for small-leak sodium–water reaction analysis in steam generators of sodium-cooled fast reactors
|
Tong, L.L.
|
|
|
126 |
C |
p.
|
artikel
|
| 18 |
Multi-state unavailability analysis of safety system redundant components with aging effect under surveillance testing
|
Mohammadhasani, F.
|
|
|
126 |
C |
p.
|
artikel
|
| 19 |
Neutronic impact of Autonomous Reactivity Control system inclusion in a breed-and-burn core
|
Keckler, Chris
|
|
|
126 |
C |
p.
|
artikel
|
| 20 |
Numerical simulation of turbulent natural convection in an enclosure with a curved surface heated from below
|
Chai, Xiang
|
|
|
126 |
C |
p.
|
artikel
|
| 21 |
Occupational internal exposure calculation during dismantling of bio-shield of Kori nuclear power plant unit#1
|
Lee, ChoongWie
|
|
|
126 |
C |
p.
|
artikel
|
| 22 |
On the use of boundary conditions and thermophysical properties of nanoparticles for application of nanofluids as coolant in nuclear power plants; a numerical study
|
Bafrani, Hamidreza Arab
|
|
|
126 |
C |
p.
|
artikel
|
| 23 |
Optimization of sensitivity analysis in best estimate plus uncertainty and the application to large break LOCA of a three-loop pressurized water reactor
|
Xiong, Qingwen
|
|
|
126 |
C |
p.
|
artikel
|
| 24 |
Reducing CO2 emissions in OECD countries: Do renewable and nuclear energy matter?
|
Saidi, Kais
|
|
|
126 |
C |
p.
|
artikel
|
| 25 |
Reformulation and evaluation of robust characteristic-based discretization for the discrete ordinates equation on structured hexahedron grids
|
Liu, Cong
|
|
|
126 |
C |
p.
|
artikel
|
| 26 |
Research on thermal hydraulic characteristics of integrated reactor in natural circulation operation under ocean motions
|
Jianbang, Wu
|
|
|
126 |
C |
p.
|
artikel
|
| 27 |
Technical feasibility study of BAEC TRIGA reactor (BTRR) as a neutron source for BNCT using OpenMC Monte Carlo code
|
Darda, Sharif Abu
|
|
|
126 |
C |
p.
|
artikel
|
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