| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Analysis of the LatticeNet neural network framework’s performance using prediction-calculated temperature coefficients in PWR assemblies
|
Furlong, Aidan
|
|
|
203 |
C |
p.
|
artikel
|
| 2 |
Application of CSA to loading pattern optimization problems for reload core in nuclear power plant
|
Hu, Yuying
|
|
|
203 |
C |
p.
|
artikel
|
| 3 |
Assessing the PLEIADES/GERMINAL V3 fuel performance code against transmutation experiments in sodium fast reactors
|
Barani, Tommaso
|
|
|
203 |
C |
p.
|
artikel
|
| 4 |
Comparison of MSLB transient results using the 3D coupled code TRACEv5p05/PARCS and the system thermal hydraulic code RELAP5
|
Stefanova, Antoaneta
|
|
|
203 |
C |
p.
|
artikel
|
| 5 |
Editorial Board
|
|
|
|
203 |
C |
p.
|
artikel
|
| 6 |
Effect analysis of oxide layer on thermal hydraulic characteristics of LBE cooled reactor
|
Wang, Chenglong
|
|
|
203 |
C |
p.
|
artikel
|
| 7 |
Evaluations of radionuclide activity releases into environment during loss of coolant accidents using the ASTEC code in pressurized water reactors within design basis and design extension conditions
|
Ederli, Stefano
|
|
|
203 |
C |
p.
|
artikel
|
| 8 |
Experimental study of supercritical carbon dioxide heat transfer deterioration in a vertical tube under high heat flux
|
Zhang, Guangxu
|
|
|
203 |
C |
p.
|
artikel
|
| 9 |
Functional failure criterion based on biaxial tensile testing of steel liners and its application to fragility analysis of nuclear containment under overpressure conditions
|
Li, Xinbo
|
|
|
203 |
C |
p.
|
artikel
|
| 10 |
Mathematical and computational models for simulating transient nuclear criticality excursions within plutonium nitrate systems
|
Daniels, J.R.
|
|
|
203 |
C |
p.
|
artikel
|
| 11 |
Numerical and optimization study of turbulent water-copper nanofluid flow in a heat exchanger in power plant with conical rings: Investigating conical ring hole diameter's influence
|
Alqaed, Saeed
|
|
|
203 |
C |
p.
|
artikel
|
| 12 |
Numerical study on lead–bismuth cross-flow induced vibration in the elastic tube bundle
|
Zhao, Hai
|
|
|
203 |
C |
p.
|
artikel
|
| 13 |
Optimisation of accident management measures to reduce iodine releases during SGTR
|
Hrdy, Bernd
|
|
|
203 |
C |
p.
|
artikel
|
| 14 |
Perturbation algorithm for refueling reactivity coefficient in the pebble-bed high temperature reactor
|
Sheng, Zhongkai
|
|
|
203 |
C |
p.
|
artikel
|
| 15 |
Pulse operation mode of inertial electrostatic plasma confinement devices
|
Prokuratov, I.A.
|
|
|
203 |
C |
p.
|
artikel
|
| 16 |
Rotation-invariant rapid TRISO-fueled pebble identification based on feature matching and point cloud registration
|
Fang, Ming
|
|
|
203 |
C |
p.
|
artikel
|
| 17 |
Simulation of in-core neutron monitoring with U-235 micro fission chamber for CiADS-like LFR
|
Pu, Neng
|
|
|
203 |
C |
p.
|
artikel
|
| 18 |
Simulation of Iodine Spiking phenomenon during Design Extended Condition type A conditions at VVER-1000 and Generic PWR
|
Zimmerl, Raphael
|
|
|
203 |
C |
p.
|
artikel
|
| 19 |
Simulation of nuclear fuel clad high-temperature ballooning under loss-of-coolant accident conditions considering anisotropic creep
|
Li, Wei
|
|
|
203 |
C |
p.
|
artikel
|
| 20 |
Study on influence of pad surface defects on lubrication characteristics of thrust bearing
|
Pu, Kexin
|
|
|
203 |
C |
p.
|
artikel
|
| 21 |
The development and assessment of the coupled thermo-mechanical code, FRAPTRAN/CUPID
|
Park, Ik Kyu
|
|
|
203 |
C |
p.
|
artikel
|
| 22 |
Thermal design and analysis of intermediate heat exchanger with alternative coolants
|
Yixiong, Sun
|
|
|
203 |
C |
p.
|
artikel
|
| 23 |
Unbalanced force analysis on valve core clamping in hydraulic spool valves
|
Zhang, Shen-zhe
|
|
|
203 |
C |
p.
|
artikel
|
| 24 |
Uncertainty calculation of thermal hydraulic simulation of DEC-A accident scenario at VVER-1000 NPP using CIAU method
|
Zimmerl, Raphael
|
|
|
203 |
C |
p.
|
artikel
|
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