8
Views
0
CrossRef citations to date
0
Altmetric
Modeling and Simulations

Neutronic Assessment and Criticality Analysis of the In-Vessel Fuel Storage Facilities in the CDT Project

, , , , , , , , , , & show all
Pages 298-301 | Published online: 10 Aug 2017

References

  • Collaborative Project “Central Design Team (CDT) for a Fast Spectrum Transmutation Experimental Facility”, Grant agreement no.FP7-232527.
  • H. A. ABDERRAHIM et al, MYRRHA, a Multipurpose hybrid Research Reactor for High-end Applications, Nuclear Physics News, Vol.20, No. 1 (2010)
  • M. SAROTTO, Preliminary FA/core design for MYRRHA/FASTEF, technical report (2010)
  • G. W. MCKINNEY, et al., MCNPX overview in:Proceedings of the 2006 HSSW, FNAL, IL, LA-UR-06-6206
  • A. HOGENBIRK, An easy way to perform a radiation damage calculation in a complicated geometry, Fusion Engineering and Design 83, 1828-1831 (2008)
  • R. E. MACFARLANE, D. W. MUIR, The NJOY Nuclear Data Processing System Version 91. Los Alamos National Laboratory, LA-12740-M. (1994)
  • J. COEN et al., Investigation of the effect of lead-bismuth eutectic on the fracture properties of T91 and 316L, Journal of Nuclear Materials 398, 122-128 (2010)

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.