Simulation of fuel dispersion in the MYRRHA-FASTEF primary coolant with CFD and SIMMER-IV-Reference-Cited by-同舟云学术

Simulation of fuel dispersion in the MYRRHA-FASTEF primary coolant with CFD and SIMMER-IV

Published:2015-12 Issue: Volume:295 Page:74-83
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Buckingham Sophia,Planquart Philippe,Eboli Marica^ORCID,Moreau Vincent^ORCID,Van Tichelen Katrien^ORCID

Funder

European SEARCH FP7

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

Reference16 articles.

1. AAVV, SIMMER IV input manual (Version 2.F)”, Research Document, O-arai Engineering Center, Japan Nuclear Cycle Development Institute, May 2102.

2. AA.VV, SIMMER III Structure model: model and method description, Research Document, O-arai Engineering Center, Japan Nuclear Cycle Development Institute, JNC TN 9400 2004-043.

3. Thermo-hydraulic analysis of the windowless target system;Bianchi;Nucl. Eng. Des.,2008

4. AFDM: An Advanced Fluid Dynamics Model, LA-11692-MS, Los Alamos National Laboratory Report, Sept.;Bohl,1990

5. Handbook on Lead-Bismuth Eutectic Alloy and Lead Properties, Nuclear Energy Agency 2007 Edition. http://www.nea.fr/html/science/reports/2007/nea6195-handbook.html.

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