nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
1 |
A fault diagnosis method for nuclear power plants rotating machinery based on deep learning under imbalanced samples
|
Yin, Wenzhe |
|
|
199 |
C |
p. |
artikel |
2 |
Analysis of buffer-IPyC separation in TRISO fuel particles
|
Krajewska, Z.M. |
|
|
199 |
C |
p. |
artikel |
3 |
Analysis of heat transfer and solidification within CANDU corium
|
Rezaee, Mahsa |
|
|
199 |
C |
p. |
artikel |
4 |
An embedded coupling design and development of NECP-Bamboo2.0 and START for PWR whole-core pin-by-pin analysis
|
Wang, Sicheng |
|
|
199 |
C |
p. |
artikel |
5 |
Comparative study of flow and heat transfer characteristics of HCF rod bundles in rectangular and triangular arrangement
|
Tang, Renwei |
|
|
199 |
C |
p. |
artikel |
6 |
Coupled performance evaluation method of heat exchanger in a lead-cooled fast reactor based on life-cycle cost and exergy analysis
|
Li, Liangxing |
|
|
199 |
C |
p. |
artikel |
7 |
Design of control strategy for reactor power control system of LBE cooled Actinide Burner Reactor (ABR) using system analysis code NUSOL-LMR
|
Mujahid, Mujtaba |
|
|
199 |
C |
p. |
artikel |
8 |
Development and assessment of a three-field subchannel code for thermo-hydraulic transient analysis under reflood conditions
|
Chen, Lin |
|
|
199 |
C |
p. |
artikel |
9 |
Development of a heat transfer model for the film boiling regime in a fouling layer
|
Wang, Xiaowen |
|
|
199 |
C |
p. |
artikel |
10 |
Dynamic multi-objective path-order planning research in nuclear power plant decommissioning based on NSGA-II
|
Zhang, Zehuan |
|
|
199 |
C |
p. |
artikel |
11 |
Editorial Board
|
|
|
|
199 |
C |
p. |
artikel |
12 |
Flow fields prediction for data-driven model of parallel twin cylinders based on POD-RBFNN and POD-BPNN surrogate models
|
Min, Guangyun |
|
|
199 |
C |
p. |
artikel |
13 |
Fuel fragmentation and relocation (FFR) model in SPACE code PART 1: Development and verification
|
Choi, Chiwoong |
|
|
199 |
C |
p. |
artikel |
14 |
Layout optimization for the high-temperature nuclear loop with movable equipment based on TMSR-LF1
|
Gong, Wei |
|
|
199 |
C |
p. |
artikel |
15 |
Modeling particle deposition in the primary circuit of pressurized water reactors for the OSCAR code
|
Cherpin, Chloé |
|
|
199 |
C |
p. |
artikel |
16 |
Model predictive control for automatic operation of space nuclear reactors: Design, simulation, and performance evaluation
|
Fu, Jianghan |
|
|
199 |
C |
p. |
artikel |
17 |
Numerical investigation of nozzle length effects on Rayleigh jet breakup behaviors and droplet formation properties at different modulation amplitudes in liquid droplet radiator
|
Zhu, Maoguo |
|
|
199 |
C |
p. |
artikel |
18 |
Numerical research on performance of new structure centrifugal compressor for supercritical CO2 power systems
|
Yu, Yongqiang |
|
|
199 |
C |
p. |
artikel |
19 |
Numerical study of anisotropic turbulence in entrance-blocked narrow rectangular channel
|
Qu, Wenhai |
|
|
199 |
C |
p. |
artikel |
20 |
Numerical study of solid-state oxygen control bypass performance and corrosion distribution in a LBE flow loop
|
Li, Hui |
|
|
199 |
C |
p. |
artikel |
21 |
Numerical study of the flow and heat transfer characteristics within the annular fuel element with double-sided cooling
|
Wu, Mingting |
|
|
199 |
C |
p. |
artikel |
22 |
Practical considerations for the adoption of Anderson acceleration in nonlinear diffusion accelerated transport
|
Shen, Qicang |
|
|
199 |
C |
p. |
artikel |
23 |
Radiological consequence assessment from long term station blackout nuclear accident on Buyende nuclear power plant of Uganda
|
Oboo, Moses |
|
|
199 |
C |
p. |
artikel |
24 |
Study of bubble migration characteristics in downward flow under SGTR accidents of LFR with similarity experiments
|
Chen, Songhui |
|
|
199 |
C |
p. |
artikel |
25 |
Submersion criticality safety analysis of an in-core reactivity control structure for space gas-cooled reactor
|
Chen, Zhiqi |
|
|
199 |
C |
p. |
artikel |
26 |
The importance of delayed neutron precursors in gamma dose calculations for activated primary heat exchanger components in the Molten Salt Breeder Reactor
|
Davidson, Eva E. |
|
|
199 |
C |
p. |
artikel |
27 |
Time-dependent leakage model for the identification of defective fuel assemblies of VVER-type nuclear reactors, part 1: Theory
|
Szalóki, Imre |
|
|
199 |
C |
p. |
artikel |
28 |
Time-dependent neutron transport method based on three-dimensional method of characteristics
|
Song, Qufei |
|
|
199 |
C |
p. |
artikel |
29 |
Turbulence budgets and statistics analysis of mixed convection liquid metal flow in horizontal channel using DNS
|
Guo, Wentao |
|
|
199 |
C |
p. |
artikel |
30 |
Two parallel methods for the three-dimensional CFD coupling simulation of shell and tube heat exchangers
|
Wang, Shiqi |
|
|
199 |
C |
p. |
artikel |
31 |
Validation of whole core transport code SHARK with HPR1000 experiment
|
Wang, Bo |
|
|
199 |
C |
p. |
artikel |
32 |
Vectorial finite element method for neutron transport solving with preconditioning GMRES acceleration
|
Wang, Yahui |
|
|
199 |
C |
p. |
artikel |