Feasibility of Using Diffusion Bonding for Producing Hybrid Printed Circuit Heat Exchangers for Nuclear Energy Applications

Author:

Saranam Venkata Rajesh,Paul Brian K.

Publisher

Elsevier BV

Subject

Artificial Intelligence,Industrial and Manufacturing Engineering

Reference33 articles.

1. Structural materials for Gen-IV nuclear reactors: Challenges and opportunities;Murty;Journal of Nuclear Materials,2008

2. O. O. N. E. US Department of Energy, "Sodium-cooled Fast Reactor (SFR) Technology and Safety Overview," ed, Feb 18, 2015.

3. A summary of sodium-cooled fast reactor development;Aoto;Progress in Nuclear Energy,2014

4. Investigation of alternative layouts for the supercritical carbon dioxide Brayton cycle for a sodium-cooled fast reactor;Moisseytsev;Nuclear Engineering and Design,2009

5. Structural assessment of intermediate printed circuit heat exchanger for sodium-cooled fast reactor with supercritical CO2 cycle;Lee;Annals of Nuclear Energy,2014

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