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                             24 results found
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
                             24 results found
 
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