Performance of structural materials in lead-based reactor coolants at temperatures up to 800C Conference Paper uri icon

abstract

  • The compatibility of structural materials with coolants in lead-based fast reactor (LFR) system at temperature 800C was analyzed. The LFR was cooled by natural convection with reactor outlet temperature of 550C. The thermal convection-based test method was used to expose materials to molten lead and lead-bismuth flowing under temperature gradient. The corrosion test results show use of selected metal alloys at high temperature and mechanical properties changed at high end LFR temperatures required for hydrogen generation.

published proceedings

  • Global 2003: Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy

author list (cited authors)

  • Runge, J. M., Leibowitz, L., Barnes, L. A., Raraz, A. G., & McDeavitt, S. M.

complete list of authors

  • Runge, JM||Leibowitz, L||Barnes, LA||Raraz, AG||McDeavitt, SM

publication date

  • December 2003