no |
title |
author |
magazine |
year |
volume |
issue |
page(s) |
type |
1 |
Analysis of flow-induced vibration of wire-wrapped fuel assemblies under the liquid metal axial flow in the Gen-IV nuclear reactor
|
Guo, Hongjian |
|
|
188 |
C |
p. |
article |
2 |
A new 103Rh Unresolved Resonance Region evaluation
|
Barry, D.P. |
|
|
188 |
C |
p. |
article |
3 |
Annular fuel neutronic analysis
|
Luiz Pereira Rebello Júnior, André |
|
|
188 |
C |
p. |
article |
4 |
Application of the hydrological model chain of the RODOS decision support system for nuclear emergencies to the analysis of possible consequences of severe accident
|
Pylypenko, O. |
|
|
188 |
C |
p. |
article |
5 |
A simplified core catcher model for the containment code AC2/COCOSYS
|
Spengler, C. |
|
|
188 |
C |
p. |
article |
6 |
Assessment of hydride precipitation modelling across fuel cladding: Hydriding in non-defective and defective fuel rods
|
Feria, F. |
|
|
188 |
C |
p. |
article |
7 |
CFD prediction of heat transfer at supercritical pressure with rough walls: Parametric analyses and comparison with experimental data
|
Kassem, S. |
|
|
188 |
C |
p. |
article |
8 |
Deep learning methods for neutron image restoration
|
Yang, Jiarui |
|
|
188 |
C |
p. |
article |
9 |
Developing a new approach for material discrimination using modular radial basis neural networks based on dual-energy X-ray radiography
|
Moshkbar-Bakhshayesh, Khalil |
|
|
188 |
C |
p. |
article |
10 |
Development of high-fidelity neutronics/thermal-hydraulics coupling system for the hexagonal reactor cores based on NECP-X/CTF
|
Li, Shuaizheng |
|
|
188 |
C |
p. |
article |
11 |
Editorial Board
|
|
|
|
188 |
C |
p. |
article |
12 |
Effects of Cr/Zircaloy-4 coating qualities for enhanced accident tolerant fuel cladding
|
Ridley, Mackenzie |
|
|
188 |
C |
p. |
article |
13 |
Experimental and analytical investigation on SMART passive safety systems for three 2-inch SBLOCA tests using SMART-ITL
|
Guk Jeon, Byong |
|
|
188 |
C |
p. |
article |
14 |
Experimental investigation of buoyancy effects on the heat transfer of supercritical carbon dioxide in a vertical tube
|
Jin, Yixuan |
|
|
188 |
C |
p. |
article |
15 |
Experimental study on convectional heat transfer characteristics of argon space in the pool-type fast reactor vessel
|
Yu, Zongyu |
|
|
188 |
C |
p. |
article |
16 |
Non-destructive analysis of spent fuel samples using a gamma-blind fast neutron detector
|
Wolfertz, Alexander |
|
|
188 |
C |
p. |
article |
17 |
Non-intrusive reduced-order modeling of radiation transport in the atmosphere
|
Halvic, Ian |
|
|
188 |
C |
p. |
article |
18 |
Nuclear data uncertainty influence on the breeding ratio in sodium-cooled fast reactor systems
|
Ryzhkov, Alexander A. |
|
|
188 |
C |
p. |
article |
19 |
Numerical study on flow-induced vibration of LBE-cooled wire-wrapped rod bundle
|
Cong, Tenglong |
|
|
188 |
C |
p. |
article |
20 |
Operational characteristics of LWR core fuelled with thorium-based fuel
|
Raj, Devesh |
|
|
188 |
C |
p. |
article |
21 |
Prediction and uncertainty quantification of SAFARI-1 axial neutron flux profiles with neural networks
|
Moloko, Lesego E. |
|
|
188 |
C |
p. |
article |
22 |
Proliferation resistance of light water reactor versus pebble bed reactor
|
Mulyana, Dany |
|
|
188 |
C |
p. |
article |
23 |
Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: First outcomes
|
Coindreau, O. |
|
|
188 |
C |
p. |
article |
24 |
Void fraction research and destructive examination of CFETR toroidal field coil protype joints
|
Xu, Yue |
|
|
188 |
C |
p. |
article |