CAST3M/ARCTURUS: A coupled heat transfer CFD code for thermal–hydraulic analyzes of gas cooled reactors-Reference-Cited by-同舟云学术

CAST3M/ARCTURUS: A coupled heat transfer CFD code for thermal–hydraulic analyzes of gas cooled reactors

Published:2007-09 Issue:15-17 Volume:237 Page:1814-1828
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Studer E.,Beccantini A.,Gounand S.,Dabbene F.,Magnaud J.P.,Paillère H.,Limaiem I.,Damian F.,Golfier H.,Bassi C.,Garnier J.C.

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

Reference12 articles.

1. Dong, Y., Sun, Y., 2003. Benchmark problem of the HTR-10 steady state temperature distribution for the full power initial core. Tech. rept. INET.

2. Dong, Y., Sun, Y., 2004. Additionnal Informations to Benchmark problem of the HTR-10 steady state temperature distribution for the full power initial core. Tech. rept. INET

3. Dumaz, P., Bassi, C., Cadiou, T., Malo, J.Y., 2005. The thermal–hydraulic studies in support to the GFR pre-conceptual design. NURETH-11 Conference, Paper 433, Avignon France.

4. Limaiem, I., Damian, F., Raepsaet, X., Studer, E., 2005. VHTR core modelling: Coupling between neutronics and thermal–hydraulics. MC2005 Conference, Paper 138, Avignon France.

5. Macnab, D.I., 1976. The CONTEMPT-G computer program and its application to HTGR containments. Tech. rept. GA-A12692A. General Atomic.

Cited by 11 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. Validation of a MELCOR model of HTR-10 in normal operation and accident conditions;Nuclear Engineering and Design;2024-05

2. Thermal hydraulic review of light water reactor based on subchannel code CTF;Nuclear Engineering and Design;2023-11

3. Ex-Core Thermofluidic Optimization for Transformational Challenge Reactor;Nuclear Science and Engineering;2022-10-12

4. Coupled radiative and conjugate heat transfer in participating media using lattice Boltzmann methods;Computers & Fluids;2016-01

5. Effect of horizontal cross flow on the heat transfer form the moderator bricks in the Advanced Gas-cooled Reactor: A CFD study;Nuclear Engineering and Design;2013-10