| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A coupled thermohydraulic/neutronic investigation of noise propagation in VVER-1000 reactor using A l 2 O 3 nanofluid coolant
|
Nourollahi, Reza
|
|
|
125 |
C |
p.
|
artikel
|
| 2 |
Adsorption of cesium and cobalt onto dried Myriophyllum spicatum L. from radio-contaminated water: Experimental and theoretical study
|
Saleh, Hosam M.
|
|
|
125 |
C |
p.
|
artikel
|
| 3 |
Advanced Gas-cooled reactors technology for enabling molten-salt reactors design - Estimation of coolant impact on neutronic performance
|
Margulis, Marat
|
|
|
125 |
C |
p.
|
artikel
|
| 4 |
Analytic evaluation of hydrogen neutron elastic scattering moments with free-gas thermal treatment compared to NJOY
|
Zhang, Yunhuang
|
|
|
125 |
C |
p.
|
artikel
|
| 5 |
An experimental study on the wall collision of micro-sized graphite particles by high-speed photomicrography
|
Zhang, Yiyang
|
|
|
125 |
C |
p.
|
artikel
|
| 6 |
An investigation on gamma-ray shielding properties of quaternary glassy composite (Na2Si3O7/Bi2O3/ B2O3/Sb2O3) by BXCOM and MCNP 6.2 code
|
Akçalı, Özgür
|
|
|
125 |
C |
p.
|
artikel
|
| 7 |
A response matrix spectral nodal method for energy multigroup X,Y-geometry discrete ordinates problems in non-multiplying media
|
da Silva, Odair Pinheiro
|
|
|
125 |
C |
p.
|
artikel
|
| 8 |
A status review on the thermal stratification modeling methods for Sodium-cooled Fast Reactors
|
Wu, Zeyun
|
|
|
125 |
C |
p.
|
artikel
|
| 9 |
Dynamic simulation of CIADS core power control based on the duty ratio of the proton beam
|
Zeng, Wenjie
|
|
|
125 |
C |
p.
|
artikel
|
| 10 |
Editorial Board
|
|
|
|
125 |
C |
p.
|
artikel
|
| 11 |
Fuzzy probability based event tree analysis for calculating core damage frequency in nuclear power plant probabilistic safety assessment
|
Purba, Julwan Hendry
|
|
|
125 |
C |
p.
|
artikel
|
| 12 |
Integral form of the control rod calibration curve in the new core configuration of HWZPR using rod insertion method
|
Kaviani, P.
|
|
|
125 |
C |
p.
|
artikel
|
| 13 |
Matrix MOC: The method of characteristics in matrix form
|
Wu, Wenbin
|
|
|
125 |
C |
p.
|
artikel
|
| 14 |
Numerical analysis of thermal stratification dependence on mass flow rate of coolant during LOFA in pools of CLEAR-S
|
Ali, Muhammad Younas
|
|
|
125 |
C |
p.
|
artikel
|
| 15 |
Oxidative dissolution of cation ion exchange resin by the Fenton process using a fluidized bed reactor
|
Huang, Chun-Ping
|
|
|
125 |
C |
p.
|
artikel
|
| 16 |
Reduced order model based FOPID controller design for power control in Pressurized Heavy Water Reactor with specific gain –phase margin
|
Lamba, Ruchika
|
|
|
125 |
C |
p.
|
artikel
|
| 17 |
Review of sub-channel code development for pressurized water reactor and introduction of CORTH-V2.0 sub-channel code
|
Deng, Jian
|
|
|
125 |
C |
p.
|
artikel
|
| 18 |
Seeking frequent episodes in baseline data of In-Situ Decommissioning (ISD) Sensor Network Test Bed with temporal data mining tools
|
Sun, Z.J.
|
|
|
125 |
C |
p.
|
artikel
|
| 19 |
The challenges of gas-cooled reactor technology for space propulsion and the development of the JANUS space reactor concept
|
Peakman, Aiden
|
|
|
125 |
C |
p.
|
artikel
|
| 20 |
The degradation of gamma-ray mass attenuation of UOX and MOX fuel with nuclear burnup
|
Atak, Haluk
|
|
|
125 |
C |
p.
|
artikel
|
| 21 |
The regional scale atmospheric dispersion analysis and environmental radiation impacts assessment for the hypothetical accident in Haiyang nuclear power plant
|
Tang, Zhihong
|
|
|
125 |
C |
p.
|
artikel
|
| 22 |
Two-phase bubbly flow simulation using CFD method: A review of models for interfacial forces
|
Khan, Irfan
|
|
|
125 |
C |
p.
|
artikel
|
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