Mixed convection and stratification phenomena in a heavy liquid metal pool-Reference-Cited by-同舟云学术

Mixed convection and stratification phenomena in a heavy liquid metal pool

Published:2015-05 Issue: Volume:286 Page:261-277
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Tarantino Mariano^ORCID,Martelli Daniele^ORCID,Barone Gianluca,di Piazza Ivan,Forgione Nicola

Funder

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference23 articles.

1. Testing and qualification of CIRCE Venturi-nozzle flow meter for large scale experiments;Agostini,2005

2. Overview of lead-cooled fast reactor activities;Alemberti;Prog. Nucl. Energy,2014

3. Testing and qualification of CIRCE instrumentation based on bubble tubes;Ambrosini;J. Nucl. Mater.,2004

4. Specification for the EFIT Core and Fuel Element Design, Deliverable D. 1.6, DM1 DESIGN, IP-EUROTRANS;Artioli,2006

5. Bandini, G., Di Piazza, I., Gaggini, P., Del Nevo, A, Tarantino, M. CIRCE experimental set-up design and test matrix definition, ENEA UTIS-TIC Technical Report, IT-F-S-001, 28.02.2011.

Cited by 37 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Code development and preliminary validation for lead-cooled fast reactor thermal-hydraulic transient behavior;Nuclear Engineering and Technology;2024-06

2. Numerical study on flow-induced vibration of LBE-cooled wire-wrapped rod bundle;Annals of Nuclear Energy;2023-08

3. Fast reactor multi-scale and multi-physics modelling at NRG;Nuclear Engineering and Design;2023-08

4. Thermo-fluid dynamic analysis of HLM pool. Circe experiments;Nuclear Engineering and Design;2023-08

5. Liquid metal cooled fast reactor thermal hydraulic research development: A review;Heliyon;2023-06