| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A direct calculation method for subcritical multiplication factor in Reactor Monte Carlo code RMC
|
Shang, Xiaotong
|
|
2018
|
118 |
C |
p. 81-91
|
artikel
|
| 2 |
A new dimensionless thermal hydraulics parameter for the heat exchangers
|
Ilyas, Muhammad
|
|
2018
|
118 |
C |
p. 154-164
|
artikel
|
| 3 |
A new Krylov subspace method based on rational approximation to solve stiff burnup equation
|
Li, Xuezhong
|
|
2018
|
118 |
C |
p. 99-106
|
artikel
|
| 4 |
A Next Generation Method for Light Water Reactor core analysis by using Global/Local Iteration Method with SP3
|
Lin, Tzung-Yi
|
|
2018
|
118 |
C |
p. 49-60
|
artikel
|
| 5 |
An improved convergence rate for the prompt α eigenvalue calculation in α-k iteration methods
|
Kia, Heydar Ali
|
|
2018
|
118 |
C |
p. 15-25
|
artikel
|
| 6 |
Anti-nuclear terrorism modeling using a flying robot as drone’s behaviors by global positioning system (GPS), detector, and camera
|
Woo, Tae Ho
|
|
2018
|
118 |
C |
p. 392-399
|
artikel
|
| 7 |
Application of advanced Rossi-alpha technique to reactivity measurements at Kyoto University Critical Assembly
|
Kong, Chidong
|
|
2018
|
118 |
C |
p. 92-98
|
artikel
|
| 8 |
Burnup characteristics analyses of graphite impurities in HTGR fuel element
|
Li, Jian
|
|
2018
|
118 |
C |
p. 165-169
|
artikel
|
| 9 |
Calculation of core safety parameters and uncertainty analyses during unprotected transients for the ALLEGRO and a sodium-cooled fast reactor
|
Batki, Bálint
|
|
2018
|
118 |
C |
p. 260-271
|
artikel
|
| 10 |
Continuous machine learning for abnormality identification to aid condition-based maintenance in nuclear power plant
|
Ayo-Imoru, R.M.
|
|
2018
|
118 |
C |
p. 61-70
|
artikel
|
| 11 |
Control of the reactor core power in PWR using optimized PID controller with the real-coded GA
|
Mousakazemi, Seyed Mohammad Hossein
|
|
2018
|
118 |
C |
p. 107-121
|
artikel
|
| 12 |
Coupled system thermal-hydraulic/CFD analysis of a protected loss of flow transient in the MYRRHA reactor
|
Toti, A.
|
|
2018
|
118 |
C |
p. 199-211
|
artikel
|
| 13 |
Discussion on emergency response capability configuration for inherent safe HTR
|
Ding, Hongchun
|
|
2018
|
118 |
C |
p. 345-352
|
artikel
|
| 14 |
Editorial Board
|
|
|
2018
|
118 |
C |
p. ii
|
artikel
|
| 15 |
Efficacy analysis of hydrogen mitigation measures of CANDU containment under LOCA scenario
|
Choi, Wonjun
|
|
2018
|
118 |
C |
p. 122-130
|
artikel
|
| 16 |
ERMSAR-2017 conference of NUGENIA/SARNET on research on severe accidents in nuclear power plants
|
Van Dorsselaere, Jean-Pierre
|
|
2018
|
118 |
C |
p. 414-416
|
artikel
|
| 17 |
Experimental study on molten metal spreading and deposition behaviors
|
Ogura, Takahito
|
|
2018
|
118 |
C |
p. 353-362
|
artikel
|
| 18 |
Experiment and modeling of jet breakup in fuel-coolant interactions
|
Bang, Kwang-Hyun
|
|
2018
|
118 |
C |
p. 336-344
|
artikel
|
| 19 |
False alarm reducing in PCA method for sensor fault detection in a nuclear power plant
|
Li, Wei
|
|
2018
|
118 |
C |
p. 131-139
|
artikel
|
| 20 |
Helium blower test based on aerodynamic force simulation
|
Zhao, Jingjing
|
|
2018
|
118 |
C |
p. 283-290
|
artikel
|
| 21 |
Melting test of penetrating tube through BWR-RPV bottom wall
|
Naitoh, Masanori
|
|
2018
|
118 |
C |
p. 212-219
|
artikel
|
| 22 |
Modelling issues related to molten pool behaviour in case of In-Vessel Retention strategy
|
Carénini, L.
|
|
2018
|
118 |
C |
p. 363-374
|
artikel
|
| 23 |
Monte Carlo modeling and simulations of AHTR fuel assembly to support V&V of FHR core physics methods
|
Ramey, Kyle M.
|
|
2018
|
118 |
C |
p. 272-282
|
artikel
|
| 24 |
Neutron transport in anisotropic random media
|
Marinosci, Alessandro
|
|
2018
|
118 |
C |
p. 406-413
|
artikel
|
| 25 |
Neutron transport solution of lattice Boltzmann method and streaming-based block-structured adaptive mesh refinement
|
Wang, Yahui
|
|
2018
|
118 |
C |
p. 249-259
|
artikel
|
| 26 |
Newton-Krylov method with nodal coupling coefficient to solve the coupled neutronics/thermal-hydraulics equations in PWR transient analysis
|
Zhang, Yijun
|
|
2018
|
118 |
C |
p. 220-234
|
artikel
|
| 27 |
Novel genetic algorithm for loading pattern optimization based on core physics heuristics
|
Israeli, E.
|
|
2018
|
118 |
C |
p. 35-48
|
artikel
|
| 28 |
Numerical methods applied to pin power reconstruction based on coarse-mesh nodal calculation
|
Pessoa, Paulo I.O.
|
|
2018
|
118 |
C |
p. 291-312
|
artikel
|
| 29 |
Optimal working fluid charge and degradation thresholds for a closed-circuit intermediate natural circulation heat transport loop
|
Fynan, Douglas A.
|
|
2018
|
118 |
C |
p. 381-391
|
artikel
|
| 30 |
Parametric study of enriched gadolinium in burnable neutron poison fuel rods for Angra-2
|
Campolina, Daniel
|
|
2018
|
118 |
C |
p. 375-380
|
artikel
|
| 31 |
Piecewise Diffusion Synthetic Acceleration scheme for neutron transport simulations in optically thick systems
|
Févotte, François
|
|
2018
|
118 |
C |
p. 71-80
|
artikel
|
| 32 |
Preliminary coupling of the Thermal/Hydraulic solvers in the Monte Carlo code MCS for practical LWR analysis
|
Yu, Jiankai
|
|
2018
|
118 |
C |
p. 317-335
|
artikel
|
| 33 |
239Pu evaluation comparison study
|
Alrwashdeh, Mohammad
|
|
2018
|
118 |
C |
p. 313-316
|
artikel
|
| 34 |
Research on the fuel loading patterns of the initial core in Chinese pebble-bed reactor HTR-PM
|
Zhang, Jingyu
|
|
2018
|
118 |
C |
p. 235-240
|
artikel
|
| 35 |
Standardized exchange of plant equipment and materials data based on ISO 15926 methodology in nuclear power plants
|
Kwon, Soonjo
|
|
2018
|
118 |
C |
p. 185-198
|
artikel
|
| 36 |
Study on bubble and liquid velocities in an area-varying horizontal channel
|
Tran, Thanh Tram
|
|
2018
|
118 |
C |
p. 170-177
|
artikel
|
| 37 |
Subplane collision probabilities method applied to control rod cusping in 2D/1D
|
Graham, Aaron
|
|
2018
|
118 |
C |
p. 1-14
|
artikel
|
| 38 |
Temperature limit in the RHR system when aligned to the ECCS
|
Lim, Jaehyok
|
|
2018
|
118 |
C |
p. 400-405
|
artikel
|
| 39 |
Thermal analysis at target for neutron generation in fissile assay
|
Lee, Yong Deok
|
|
2018
|
118 |
C |
p. 241-248
|
artikel
|
| 40 |
Thermal hydraulic analysis of loss of flow accident in the JRR-3M research reactor under the flow blockage transient
|
Guo, Yuchuan
|
|
2018
|
118 |
C |
p. 147-153
|
artikel
|
| 41 |
The sensitivity analysis for IHTS and SG due to the Large-scale Sodium-Water Reaction event in PGSFR
|
Ahn, Sang June
|
|
2018
|
118 |
C |
p. 26-34
|
artikel
|
| 42 |
Validation of PSI best estimate plus uncertainty methodology against SPERT-III reactivity initiated accident experiments
|
Dokhane, A.
|
|
2018
|
118 |
C |
p. 178-184
|
artikel
|
| 43 |
Wide pressure range condensation modeling on pure steam/steam-air mixture inside vertical tube
|
Chung, Young-Jong
|
|
2018
|
118 |
C |
p. 140-146
|
artikel
|
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